05000255/LER-2005-001, Regarding Reactor Protection System and Auxiliary Feedwater System Actuation
| ML050740131 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/03/2005 |
| From: | Domonique Malone Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 05-001-00 | |
| Download: ML050740131 (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)(1) 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) |
| 2552005001R00 - NRC Website | |
text
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)Palisades Nuclear Plant Commhted to Nuhrxclee_
COperated by Nuclear Management Company, LLC March 3, 2005 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 05-001, Reactor Protection System and Auxiliary Feedwater System Actuation Licensee Event Report (LER)05-001 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).
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Daniel J. Malone Site Vice President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosure (1)
CC Administrator, Region 1II, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC 27780 Blue Star Memorial Highway
- Covert, Michigan 49043-9530 Telephone: 269.764.2000
ENCLOSURE 1 LER 05-001, REACTOR PROTECTION SYSTEM AND AUXILIARY FEEDWATER SYSTEM ACTUATION 2 Pages Follow
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 learned are incorporated Into the licensing process and fed back to Industry.
LICENSEE EVENT REPORT (LER)
Send comments regarding burden estimate to the Records and FOI.APrivacy Service Branch (T-5 F52), U.S. Nuclear RegulatoryCommission.Washington, DC 20555-0001, orbyintemet e-( ereverse for required number of mail to Infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory (See re
- fAffairs, NEOB-10202, (3150-0066). Office of Managementand Budget.Washington, DC20503.
digits/characters for each block)
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FACIUTY 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 FACILITIES INVOLVED (8)
I FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMBER NO MO DAY YEAR 01 09 2005 2005
-- 001 00 03 03 2005 FACILITY NAME DOCKETNUMBER OPERATING 1
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR D: (Check all that apply) (11)
MODE (9) l 20.2201(b) l 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B)
_ 50.73(a)(2)(ix)(A)
POWER 7
20.2201(d) 20.2203(a)(4) 50.73(a)(2)(iii) l 50.73(a)(2)(x)
LEVEL (10) 5 20.2203(a)(1)
= 50.36(c)(1)(i)(A)
X 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(aX2)(i) 50.36(c)(1)(iiXA) 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)
NRC FOnT 366A 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)(1)(C) 50.73(a)(2)(viii)(A) 20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(B)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Barb Dotson (269) 764-2265 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13)
MANU-REPORTABLE A-NU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX
CAUSE
SYSTEM COMPONENT FA CTURER TO EPIX X
TF DRN W120 Y l SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR YES (f y.
c e EOSUBMISSION gYES (If yes, complete EXPECTED SUBMISSION DATE).
X (NO l
DAE1)
ABSTRACT On January 9, 2005, at 1117 hours0.0129 days <br />0.31 hours <br />0.00185 weeks <br />4.250185e-4 months <br />, with the plant operating at approximately 100% power, a rapid plant down power was commenced following an unexpected lowering of condenser vacuum. At 1127 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.288235e-4 months <br />, the reactor was manually tripped from 75% power. Following the reactor trip, the auxiliary feedwater system started automatically to maintain steam generator water level. The plant was stabilized in Mode 3 to investigate and repair the cause of the low condenser vacuum. 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.
4lRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE 3 YEA SEQUENTIAL I REVISION I YEARI NUMBER NUMBER 2Of2 Palisades 05000-255 2005 001 00 TEXT (Ifmore space is required, use additional copies of NRC Form 366A) (17)
EVENT DESCRIPTION
On January 9, 2005, at 1 117 hours0.00135 days <br />0.0325 hours <br />1.934524e-4 weeks <br />4.45185e-5 months <br />, with the plant operating at approximately 100% power, a rapid plant down power was commenced following an unexpected lowering of condenser [COND;SG]
vacuum. At 1127 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.288235e-4 months <br />, the reactor [RCT;ABI was manually tripped from 75% power. Following the reactor trip, the auxiliary feedwater system [BA] started automatically to maintain steam generator [SG;SB] water level. The plant was stabilized in Mode 3 to investigate and repair the cause of the low condenser vacuum. 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 [JC] and automatic actuation of the auxiliary feedwater system.
CAUSE OF THE EVENT
A low pressure turbine casing drain line, which was routed through the condenser, had not been capped as part of a plant modification that had intended to permanently plug all of the low pressure turbine casing drains. The uncapped casing drain line failed, allowing air in-leakage to the condenser, which caused the lowering of condenser vacuum.
SAFETY SIGNIFICANCE
The safety significance of this event was minimal. All safety systems functioned as expected during the plant trip.
CORRECTIVE ACTIONS
The low pressure turbine casing drain was permanently plugged.
PREVIOUS SIMILAR EVENTS
None.