05000270/LER-2006-001, Re Loss of Isolation During Pump Instrument Check Results in Reactor Trip
| ML061710471 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/12/2006 |
| From: | Brandi Hamilton Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 06-001-00 | |
| Download: ML061710471 (15) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(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 |
| 2702006001R00 - NRC Website | |
text
kDuke WEnergy BRUCE H HAMILTON Vice President Oconee Nuclear Station Duke Energy Corporation ONOIVP / 7800 Rochester Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax bhhamilton@duke-energy. corn June 12, 2005 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555
Subject:
Oconee Nuclear Station Docket Nos. 50-270 Licensee Event Report 270/2006-01, Problem Investigation Process No.:
Revision 0 0-06-2079 Gentlemen:
Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report 270/2006-01, Revision 0, regarding a Unit 2 reactor trip following a trip of a reactor coolant pump during a maintenance activity.
This report is being submitted in accordance with 10 CFR 50.73 (a)(2)(iv)(A).
This event is considered to be of no significance with respect to the health and safety of the public.
Very truly
- yours, Bruce H. Hamilton, Vice President Oconee Nuclear Site Attachment www. duke-enerey. corn
Document Control Desk Date: June 12, 2006 Page 2 cc:
Mr. William D. Travers Administrator, Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, S. W.,
Suite 23T85 Atlanta, GA 30303 Mr.
L.
N. Olshan Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 Mr.
M. C.
Shannon NRC Senior Resident Inspector Oconee Nuclear Station Mr.
D.
W. Rich NRC Senior Resident Inspector Oconee Nuclear Station INPO (via E-mail)
Date: June 12, 2006 Page 3 bxc:
ONS Site:
bxc: ONS Site:
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Edge#
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GO:
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Thomas NGO Serv: R.G. Hull#
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Jeff Rowell Hardcopy - All others by E-Mail Distribution Copied By Request:
- - All others by Directive (Revised 1-17-2006)
NRC FORM 336 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (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 learned are incorporated into the licensing process and fed back to industry. Send LICENSEE EVENT REPORT (LER) comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52).
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. Ifa (See reverse for required number of means used to impose an information collection does not display a currently valid OMB control digits/characters for each block) number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME 2.DOCKETNUMBER 3.PAGE Oconee Nuclear Station, Unit 2 05000-0270 1 OF 7
- 4. TITLE Loss of Isolation during Pump Instrument Check Results in Reactor Trip
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SI FACILITY NAME DOCKET NUMBER SEQUENTIAL REV MO DAY YEAR YEAR NUMBER NO MO DAY YEAR None 05000 FACILITY NAME DOCKET NUMBER 04 12 2006 2006
- - 001
- - 00 06 12 06 None 05000
- 9. OPERATING MODE
- 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) 1 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)
- 10. POWER LEVEL 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) 100 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 I_
_or in
Abstract
On April 12, 2006, while operating at 100% in Mode 1, Oconee Nuclear Station Unit 2 experienced a reactor trip.
The post trip response was normal, with all major operating parameters remaining within expected limits.
Operators took appropriate action to stabilize the unit in Mode 3.
The cause of the event was determined to be a trip of a reactor coolant pump during testing of a pump power transducer.
The pump trip occurred due to a loss of isolation between the power transducer being tested and the operating circuit while connected to the test equipment.
Corrective actions address changes to restrict use of this procedure on critical equipment while operating.
This event is considered to have no significance with respect to the health and safety of the public.
NRC FORM 366 (7-2001)
NRC FORM 36GA U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
- 1. FACILITY NAME
- 2. DOCKET
- 6. LER NUMBER
- 3. PAGE I SEQUENTIAL I REVISION YEAR NUMBER NUMBER Oconee Nuclear Station, Unit 2 05000270 06 01 00 2
OF 7
- 17. NARRATIVE (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 (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)
Large Early Release Frequency (LERF) Significance Impact The LERF significance of this event has been evaluated quantitatively using the same considerations as for the CDS Impact.
The event has an insignificant impact on the core damage risk.
Therefore, there was no actual impact on the health and safety of the public due to this event.
ADDITIONAL INFORMATION
A review of Unit trip events over the last five years indicates that there have been no similar reactor trip events at Oconee within that time period.
There were no releases of radioactive materials, radiation exposures or personnel injuries associated with this event.
The trip of the reactor constitutes a Maintenance Rule functional failure and is considered reportable under the Equipment Performance and Information Exchange (EPIX) program.
ENCLOSURE 1 SIGNATURE SHEET PIP 0-06-2079 Prepared By:
Revised By:
Reviewed By:
Approved By:
- Manager, RGC Reviewed By:
Station Manager Date:
Date:
Date:
Date:
Date:
Date:
Date:
Date:
Date:
Date:
ENCLOSURES:
- 1. Regulatory Compliance Signature Sheet
- 2. References
- 3. Corrective Action Schedule
- 4. Personnel Contacted
- 5. Cause Code Summary
ENCLOSURE 2 REFERENCES PIP 0-06-2079 PIP 0-06-2079 Root Cause Report Post Trip Review Procedure (PT/0/A/0811/002) Trip 100 (completed procedure approved 4-24-06)
E-mail Dated 05/30/2006 From Sarah L Chisholm (PRA Group) with LER input from PRA Group UFSAR Section 7.2.2 OEE-217-10 (Rev 010, per NEDL)
OSS-254.00-00-1033 Rev 19 RCS DBD (Section 5.3.1.4 on Reactor Coolant Pump 2B2)
ENCLOSURE 3 CORRECTIVE ACTION SCHEDULE PIP 0-06-2079 CORRECTIVE ACTION PERSON(S)
CONTACTED PERSON(S)
ASSIGNED TO DUE DATE 1
(From Root Cause Report)
ENCLOSURE 4 PERSONNEL CONTACTED PIP 0-06-2079 Ray Smith (OPS)
Jeff Rowell (RES)
Chad Hitt (RES)
Jim Kiser (MCE Valves)
Bill Rostron (RES)
Preston Gillespie (RES)
Eddie Anderson (OPS)
Sarah Chisholm (PRA Group)
Dennis Smith (I&E)
ENCLOSURE 5 CAUSE CODE ASSIGNMENT SHEET PIP 0-06-2079 CAUSE CODES:
M2o Unanticipated Interaction Between Systems or Components