05000255/LER-2004-001, Regarding Reactor Protection System and Auxiliary Feedwater System Actuation
| ML043010195 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/13/2004 |
| From: | Domonique Malone Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 04-001-00 | |
| Download: ML043010195 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(B) |
| 2552004001R00 - NRC Website | |
text
V Committed to Nuclear Excetllec Palisades Nuclear Plant Operated by Nuclear Management Company, LLC October 13, 2004 10 CFR 50.73(a)(2)(iv)(A)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Licensee Event Report 04-001, Reactor Protection System and Auxiliary Feedwater System Actuation Licensee Event Report (LER)04-001 is attached. The LER describes a manual actuation of the reactor protection system and subsequent actuation of the auxiliary feedwater system. This event is reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A).
Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.
17w Daniel J. Malone Site Vice President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosure (1)
CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC 27780 Blue Star Memorial Highway
- Covert, Michigan 49043-9530 Telephone: 269.764.2000
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ENCLOSURE I LER 04-001, REACTOR PROTECTION SYSTEM AND AUXILIARY FEEDWATER SYSTEM ACTUATION 2 Pages Follow
I NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2007 (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 teamed are incorporated into the licensing process and fed back to Industry.
LICENSEEEVENTREPORT(LER)
Send comments regarding burden estimate to the Records and FOWPrivacy Service Branch (T-5 F52). U.S. Nuclear RegulatoryCommission, Washington, DC 20555-001, orbyintemete-(See reverse for required number of mail to lnfocollects0 nrc.gov. and to the Desk Officer, Office of Information and Regulatory (SeeAffairs.
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FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Palisades Nuclear Plant 05000-255 1 of 2
TITLE (4)
Reactor Protection System and Auxiliary Feedwater System Actuation EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACIUTIES INVOLVED (8)
_EV FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMBER NO MO DAY YEAR 08 31 2004 2004 -- 001
-- 00 10 13 2004 FACILITY NAME DOCKET NUMBER OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR,: (Check all that apply) (11)
MODE (9) 20.2201(b)
= 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 95(0
_ 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (10) _
20.2203(a)(1) 50.36(c)(1)(i)(A)
X 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A)
O 50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii)
_ 50.36(c)(2)
_ 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Specify In Abstract below or In 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) 20.2203(a)(2)(v)
= 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 20.2203(a)(2)(vi)
_ 50.73(a)(2)(i)(C) 50.73(a)(2)(viii)(A)
.20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(B) l
_4 LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Barb Dotson 1
(269) 764-2265 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13)
MANU-REPORTABLE MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX
CAUSE
SYSTEM COMPONENT FA CTURER TO EPIX D
SD MO A180 N
SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR SUBMISSION YES (if yes, complete EXPECTED SUBMISSION DATE).
I X INO DATE (115) 1 ABSTRACT On August 31, 2004, at 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />, the plant was operating at approximately 100% power. A rapid plant down power was commenced following report of a fire in the vicinity of the P-2B condensate pump lower motor bearing.' At 0718 hours0.00831 days <br />0.199 hours <br />0.00119 weeks <br />2.73199e-4 months <br />, the reactor was manually tripped from approximately 95% power, in conjunction with securing the P-2B condensate pump, and the imminent loss of main feedwater. Following the reactor trip, the auxiliary feedwater system started automatically to maintain steam generator water level. The plant was stabilized in Mode 3. Overheating, and ultimately fire, at the condensate pump lower motor bearing were caused by pump and motor misalignment following maintenance in July 2004. The pump and motor misalignment occurred as a result of inadequate maintenance instructions. Proper alignment criteria were established and incorporated into the work instruction when the repaired motor was reinstalled in September 2004.
The safety significance of this event was minimal. All safety systems functioned as expected during the plant trip.
This event is reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A) as an event that resulted in a manual actuation of the reactor protection system and automatic actuation of the auxiliary feedwater system.
s a.
^U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
YEAR SEQUENTIAL REVISION 2
1 UMBER INUMBER 2f Palisades 05000-255 2004 001 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
EVENT DESCRIPTION
On August 31, 2004, at 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />, the plant was operating at approximately 100% power. A rapid plant down power was commenced following report of a fire in the vicinity of the P-2B condensate pump [P;SD] lower motor [MO] bearing. At 0718 hours0.00831 days <br />0.199 hours <br />0.00119 weeks <br />2.73199e-4 months <br />, the reactor was manually tripped from approximately 95% power, in conjunction with securing P-2B condensate pump, and the imminent loss of main feedwater [SJ]. Following the reactor trip, the auxiliary feedwater system [BA] started automatically to maintain steam generator [SG] water level. The plant was stabilized in Mode 3.
This event is reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A) as an event that resulted in a manual actuation of the reactor protection system [JC] and automatic actuation of the auxiliary feedwater system.
CAUSE OF THE EVENT
Overheating, and ultimately fire, at the condensate pump lower motor bearing were caused by pump and motor misalignment following maintenance in July 2004. The pump and motor misalignment occurred as a result of inadequate maintenance instructions.
SAFETY SIGNIFICANCE
The safety significance of this event was minimal. All safety systems functioned as expected during the plant trip.
CORRECTIVE ACTIONS
Proper alignment criteria were established and incorporated into the work instruction when the repaired motor was reinstalled in September 2004.
PREVIOUS SIMILAR EVENTS
None.