05000400/LER-2007-002, Control Rod Shutdown Bank Anomaly Causes Entry Into Technical Specification 3.0.3
| ML072330121 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/13/2007 |
| From: | Mccartney E Progress Energy Carolinas, Progress Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-07-110 LER 07-002-00 | |
| Download: ML072330121 (5) | |
| 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 |
| 4002007002R00 - NRC Website | |
text
A Nagms Elmwgy Serial: HNP-07-110 10 CFR 50.73 AUG 13 2007 U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555
Subject:
Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/License No. NPF-63 Licensee Event Report 2007-002-00 Ladies and Gentlemen:
The enclosed Licensee Event Report 2007-002-00 is submitted in accordance with 10 CFR 50.73. This report describes a control rod shutdown bank anomaly whereby the plant entered Technical Specification 3.0.3. This event is reportable under 10 CFR 50.73(a)(2)(i)(B).
Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor -
Licensing/Regulatory Programs, at (919) 362-3137.
Sincerely, Eric A. McCartney 0
Plant General Manager Harris Nuclear Plant EAM/kms
Enclosure:
cc:
LER 2007-02 "Control Rod Shutdown Bank Anomaly Causes Entry into Technical Specification 3.0.3" Mr. P.B. O'Bryan, NRC Sr. Resident Inspector Ms. M.G. Vaaler, NRC Project Manager Dr. W.D. Travers, NRC Regional Administrator Progress Energy Carolinas, Inc.
Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562
~c22
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may sfor each block)nnot conduct or sponsor, and a person is not required to respond to, the digits/characters frecblk)information collection.
l3. PAGE Harris Nuclear Plant - Unit 1 05000400 1 OF 4
- 4. TITLE Control Rod Shutdown Bank Anomaly Causes Entry into Technical Specification 3.0.3
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE 1
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR SEQUENTIAL REV I FACILITY NAME DOCKET NUMBER MOTURYEAR EUER E
MONTH DAY YEAR N/A 05000 IFACILITY NAME DOCKET NUMBER 06 12 2007 2007 -
002 -
00 08 13 2007 1N/A 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[1 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii) 1 El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
[I 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
[I 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 100 El 20.2203(a)(2)(v)
[I 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER [3 20.2203(a)(2)(vi)
ED 50.73(a)(2)(i)(B)
El 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 NRC Form 366A)
III. PREVIOUS SIMILAR EVENTS
LER 2004-003 dated July 2, 2004, was associated with an automatic reactor trip due to a Rod Control Power Cabinet Card failure. Diagnostic tests and visual examinations were completed for the installed Power Cabinet Cards but not for the Logic Cabinet Cards. However, this type of test is static in nature and it is unlikely that it would have predicted or detected the type of age related failure associated with the Master Cycler Counter Card.
LER 2007-001 dated May 8, 2007, was generated for a rod control urgent alarm due to a failed Slave Cycler Logic Card in the Westinghouse Rod Control System. The most likely mechanism for the Slave Cycler Logic Card failure is aging of a Z4 chip. A planned corrective action is to establish a structured program of card replacements.
IV. CORRECTIVE ACTIONS
Completed corrective actions included the replacement of the failed A 104 Master Cycler Counter Card on June 26, 2007. A planned corrective action is to establish a structured program of card replacements and to ensure the appropriate equivalency evaluations are completed. This action is being tracked through the corrective action program.
V.
COMMITMENTS
This document contains no new regulatory commitments.