05000400/LER-2007-001, Regarding Control Rod Shutdown Bank Anomaly Causes Entry Into Technical Specification 3.0.3
| ML071360095 | |
| Person / Time | |
|---|---|
| Site: | Harris  (NPF-063) |
| Issue date: | 05/08/2007 |
| From: | Mccartney E Progress Energy Carolinas, Progress Energy Co |
| To: | Document Control Desk, Plant Licensing Branch III-2 |
| References | |
| HNP-07-064 LER 07-001-00 | |
| Download: ML071360095 (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 |
| 4002007001R00 - NRC Website | |
text
Progress Energy Serial: HNP-07-064 10 CFR 50.73 MAY 0 8 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 2007-001-00 Ladies and Gentlemen:
The enclosed Licensee Event Report 2007-001-00 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 cate Plant General Manager Harris Nuclear Plant EAM/sfm
Enclosure:
LER 2007-01 "Control Rod Shutdown Bank Anomaly Causes Entry into Technical Specification 3.0.3" cc:
Mr. P.B. O'Bryan, NRC Sr. Resident Inspector Mr. L.M. Regner, 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
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct digits/characters for each block) or sponsor, and a person is not required to respond to, the information collection.
l3.
PAGE Harris Nuclear Plant - Unit 1 05000400
- 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 YEAR SEQUENTIAL REV MONTH FACLITY NAME DOCKET NUMBER NUMBER NO.
N/A 05000 FACILITY NAME DOCKET NUMBER 03 09 2007 2007 001 -
00 05 08 2007 N/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)
[l 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 20.2201(d)
El 20.2203(a)(3)(ii) 0l 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
[I 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 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)
[I 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)
[] 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)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
Z 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)
IV. 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 Slave Cycler Logic 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 Slave Cycler Logic Card. The planned corrective action below for establishing a structured card replacement program should diminish the frequency of rod control card failures.
V. CORRECTIVE ACTIONS
Completed corrective actions include replacing the failed Slave Cycler Logic Card. A planned corrective action is to establish a structured program of card replacements. This action is being tracked through the corrective action program.
VI. COMMITMENTS
This document contains no new regulatory commitments.