05000400/LER-2004-006, Regarding Manual Actuation of Auxiliary Feedwater Pump
| ML050120123 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/06/2005 |
| From: | Waldrep B Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EN 41179, HNP-04-163 LER 04-006-00 | |
| Download: ML050120123 (8) | |
| 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 |
| 4002004006R00 - NRC Website | |
text
Progress Energy U.S. Nuclear Regulatory Commission ATrN: NRC Document Control Desk Washington, DC 20555 Serial: HNP-04-163 10CFR50.73 JAN 0 6 2005 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 LICENSEE EVENT REPORT 2004-006-00 Ladies and Gentlemen:
The enclosed Licensee Event Report 2004-006-00 is submitted in accordance with 10 CFR 50.73. This initial report describes an event in which a motor driven auxiliary feedwater pump was manually started in response to lowering steam generator level. At the time of the event, the plant was in Mode 1 and reactor power was approximately 7%. Event Notification EN 41179 previously reported this event in accordance with 10 CFR 50.72.
Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor -
Licensing/Regulatory Programs, at (919) 362-3137.
Sincerely,
,4Ce AS -)
B. C. Waldrep Plant General Manager Harris Nuclear Plant BCW/bcm Enclosure C:
Mr. R. A. Musser (HNP Senior NRC Resident)
Mr. C. P. Patel (NRC-NRR Project Manager)
Dr. W. D. Travers (NRC Regional Administrator, Region II)
Progress Energy Carolinas. Inc.
Harris Nuclear Plant P.O. Box 165 New Hill, NC 27562 j
I-.
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRCmaynotconduct or sponsor, and a person Is not required to respond to, the Information digits/characters for each block) collection.
- 3. PAGE Harris Nuclear Plant - Unit 1 05000400 1 OF 7
- 4. TITLE Manual Actuation Of Auxiliary Feedwater Pump
- 5. EVENT DATE
- 6. LER NUMBER l
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUNILRVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEUENTUALBREVR MONTH DAY YEAR N/A 05000 FACILITY NAME DOCKET NUMBER 11 07 2004 2004 - 006 -
00 01 06 2005 N/A 05000
- 9. OPERATING MODE
.THISREPORTISSUBMTTEDPURSUANT TO THEREUIREMENTS OF10CFR§: (Check allthatapply) o 202201(b)
El 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 10 20.2201 (d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A) o 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) l 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0
20.2203(a)(2)(ii) a 50.36(c)(1)(Ii)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x) 0 202203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) o 202203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 007 a 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER o 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
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During RFO-09, following the two stem failures described above and in response to a maintenance history of actuator problems and stem failures, the MFIVs were modified. This modification included design changes to the actuator and valve internals. The failures described in the subject LER (LER 2004-006) are the first MFIV failures since the installation of the valve modification in RFO-09.
While the two previous events also involved design deficiencies, the deficiencies were sufficiently different from those identified during this event that prior corrective actions would not have been expected to prevent the MFIV failures that are the subject of this LER.