05000368/LER-2008-002, Manual Reactor Trip from Hot Standby Conditions Due to Perceived Inoperability of Individual Control Element Assembly Position Indication
| ML081550669 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  (NPF-006) |
| Issue date: | 06/03/2008 |
| From: | James D Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2CAN060801 LER 08-002-00 | |
| Download: ML081550669 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 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 |
| 3682008002R00 - NRC Website | |
text
2CAN060801 June 3, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Licensee Event Report 50-368/2008-002-00 Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
In accordance with 10CFR50.73(a)(2)(IV)(A), enclosed is the subject report concerning a manual reactor trip from Hot Standby conditions.
There are no new commitments contained in this submittal.
Sincerely, DEJ/rs Enclosure Dale E. James Manager, Licensing - ANO Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619
2CAN060801 Page 2 cc:
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 (6-2004)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-2004)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Arkansas Nuclear One - Unit 2
- 2. DOCKET NUMBER 05000368
- 3. PAGE 1 of 3
- 4. TITLE Manual Reactor Trip From Hot Standby Conditions Due to Perceived Inoperability of Individual Control Element Assembly Position Indication
- 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 4
7 2008 2008 - 002 - 00 6
6 2008 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERATING MODE 3
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 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) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 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 20.2203(a)(2)(vi) 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 NRC Form 366A)
D.
Corrective Actions
A Lessons Learned document was prepared by the involved SM and was distributed to the SMs for both ANO units.
E.
Safety Significance
The reactor was sub-critical at the time of this event with boron concentration established for the performance of CEA drop time testing. As a result, the insertion of the CEAs (approximately 2 inches) had no measurable impact on reactivity. Considering these facts and that the SMs action in opening the trip breakers was conservative in nature, this event was of no safety significance F.
Basis for Reportability A manual reactor trip is reportable pursuant to 10CFR50.73(a)(2)(IV)(A). In addition, this event was reported to the NRC Operations Center at 1957 CST on April 7, 2008, in accordance with 10CFR50.72(b)(3)(iv)(A)
G.
Additional Information
There have been no previous similar events reported by ANO.