05000400/LER-2005-002, Regarding Manual Reactor Trip Following a Trip of the B Condensate Pump Motor
| ML051940424 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/30/2005 |
| From: | Waldrep B Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-05-077 LER 05-002-00 | |
| Download: ML051940424 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 4002005002R00 - NRC Website | |
text
8j Progress Energy IUN 3 0 2005 U.S. Nuclear Regulatory Commission Serial: HNP-05-077 ATTN: NRC Document Control Desk 10 CFR 50.73 Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT I DOCKET NO. 50-400/LICENSE NO. NPF-63 LICENSEE EVENT REPORT 2005-002-00 Ladies and Gentlemen:
The enclosed Licensee Event Report 2005-002-00 is submitted in accordance with 10 CFR 50.73. This report describes a manual reactor trip following trip of the "B" condensate pump motor. In accordance with 10 CFR 50.72, this was previously reported on May 1, 2005. Refer to Event Number 41654.
Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor -
Licensing/Regulatory Programs, at (919) 362-3137.
Sincerely, A{4o B. C. Waldrep Plant General Manager Harris Nuclear Plant BCW/sfm 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. 0. Box 165 New Hill, NC. NC 27562
Tlv-_''-'i'-r I TT I
I NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 06130/2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons teamed are Incorporated Into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIAiPrlvacy Service Branch (T.5 F52), U.S. Nuclear LICENSEE EVENT REPORT (LER)
RegulatoiyCommission.Washington.DC 20555-001. orby Internet e-mail to lnfoollctsnrcgov.andto he eskOfficer. Office oInformation and RegtlatoryAleairs.NEOB-10202(3150-0104),Offce of Managemntand Budget.
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W Washlngton.:DC 20503. If a means used to Impose an Informalon collecton (See reverse for required fifnuiber of doesnotdisptayacurrenflyvalidOMBcontrolnwmbertheNRCmaynotconduct digits/characters for each block) or sponsor, and a person Is not required to respond to, the Information
- 1. FACILITY NAMVE
- 2. DOCKET NUMBER
- 3. PAGE
- - Harris Nuclear Plant - Unit 1 05000400 1 OF 3
- 4. TITLE Manual Reactor Trip Following a Trip of the "B" Condensate Pump Motor
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR N/A 05000 j j
~NUMBER NO.
0 FACILITY NAME DOCKET NUMBER 05 01 2005 2005 - 002 -
00 06 30 2005 N/A 05000 9.OPERATING MODE 11.THIS REPORTISSUBMITTEDPURSUAITTOTHE REQUIREMENTS OF10 CFR§: (Checkallthatapply) o 20.2201(b) 0 20.2203(aX3)(i) 0 50.73(a)(2)(IXC) 0 50.73(a)(2Xvil) 1 0 20.2201(d) 0 20.2203(a)(3)(11) 0 50.73(aX2)(ii)(A) 0 50.73(a)(2Xviii)(A) 0 20.2203(aXl) 0 20.2203(aX4) 0 50.73(aX2)(ii)(B) 0 50.73(a)(2XvIli)(B) 0o 20.2203(aX2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(aX2)(iii) 0 50.73(a)(2XixXA)
- 10. POWER LEVEL 0
20.2203(aX2Xii)
D 50.36(cX1)(iiXA) 0 50.73(aX2XivXA) 0 50.73(a)(2Xx) o 20.2203(aX2)(lii) 0 50.36(cX2) 0 50.73(aX2Xv)(A) 0 73.71(aX4) o 20.2203(aX2)(iv) 0 50.46(aX3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71(aX5) 100 [3 20.2203(aX2Xv) 0 50.73(aX2)(iXA) 0 50.73(a)(2XvXC) 0 OTHER ol 20.2203(aX2Xvi) 0 50.73(aX2)(i)(B) 0 50.73(a)(2XvXD)
Specify In Abstract below or In (If more space Is required, use additional copies of (If more space Is required, use additional copies of iJRC Form 366A)
Ill. SAFETY SIGNIFICANCE Other than the transient Induced by the manual reactor trip, there were no safety significant consequences as a result of this event. The plant was manually tipped by control room operators as directed by plant procedures. The plant Is designed for a loss of main feedwater, and it responded as expected for this condition. The loss of normal feedwater event is classified as an ANS Condition II event, a fault of moderate frequency (i.e., expected to occur, in general, r.o more than once per year). The init'al plant conditions were well within the bounding conditions for the plant design. The event did not involve any release of radioactive material. No design safety limits were exceeded, and no fission product barriers or components were damaged as a result. The plant was promptly stabilized at normal operating no-load reactor coolant system temperature and pressure, and no unusual conditions were observed for plant equipment following the manual reactor trip. All safety equipment functioned as required. The operating staff performed all required actions for the trip.
The potential safety consequences under other alternate conditions, such as a loss of both MFPs, may have increased the severity of the transient and may have resulted In an automatic rather than manual reactor trip, but these alternate conditions would not have significantly increased the potential safety consequences of this event. In general, the severity of the plant transient is reduced at lower power levels, so the same event initiated at a lower power (i.e., less than 100% power) would be expected to result in a smaller transient. This report is submitted pursuant to 1 OCFR50.73(a)(2)(iv)(A) for the manual reactor trip and automatic actuation of the AFW system.
IV. CORRECTIVE ACTIONS
Completed corrective actions include replacing the failed motor. Planned corrective actions include improving process controls for shaft weld repairs and subsequent non-destructive examination, improving seal installation techniques, establishing coupling inspection criteria, and improving monitoring capability of the CPs.
V. PREVIOUS SIMILAR EVENTS
HNP LER 2003-005-00 (reported October 16, 2003)
The WA" CP motor failed on August 17, 2003 prompting an operator Initiated manual reactor trip due to loss of feedwater. This event was investigated in non-conformance report AR-1 03182. The cause of this unplanned trip of the "A" CP motor was due to a lightning voltage surge that overcame the dielectric strength of the motor winding Insulation (i.e., an electrical short). In addition, the grounding system was not effective at protecting the OA" CP motor from a lightning strike. Corrective actions Included replacing the failed motor and installing surge protection. In addition, HNP enhanced the "A' CP grounding system and install surge protection on the "B" CP motor. Although the root cause for this previous event is significant In relation to the subject event, the previous corrective actions would not have prevented the event Identified by this LER.
The INPO operating experience database and EPIX database were searched by pump and motor model number. Keyword searches were also conducted on shaft cracking. There was no OE identified that was directly applicable to the experienced failure and that would have prevented the event. This event was not a repeat failure.
VI. COMMITMENTS
This document contains no new regulatory commitments.