05000255/LER-2006-003, Re Completion of Plant Shutdown Required by Technical Specifications
| ML061500079 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/26/2006 |
| From: | Harden P Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 06-003-00 | |
| Download: ML061500079 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv), System Actuation 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 |
| 2552006003R00 - NRC Website | |
text
Palisades Nuclear Plant Operated by Nuclear Management Company, LLC May 26,2006 10 CFR 50.73(a)(2)(i)(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 06-003, Completion Of Plant Shutdown Required Bv Technical Specification's Licensee Event Report (LER)06-003 is enclosed. The LER describes the completion of a plant shutdown required by the Technical Specifications.and is reportable in accordance with 10 CFR 50.73(a)(2)(i)(A).
Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.
Paul A. Harden 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
ENCLOSURE 1 LER 06-003, Completion Of Plant Shutdown Required By Technical Specifications 3 Pages Follow
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 31 50-01 04 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 FOINPrivacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-(See reverse for required number of mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0066), Office of Management and Budget, Washington, DC 20503.
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FACILITY NAME (1)
DOCKET NUMBEH (2)
PAGE (3)
Palisades Nuclear Plant 05000-255 1 of 3
TITLE (4)
Completion Of Plant Shutdown Required By Technical Specifications EVEKT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
FACILITY NAME DOCKET NUMBER SEQUENTIAL REV MO DAY YEAR YEAR NUMBER NO MO DAY YEAR 03 FAClLrrY NAME DOCKET NUMBER 29 2006 2008 -- 003 -- 00 05 26 2006 I
OPERATING E -
REQUIREMENTS OF 10 CFR.: (Check hll that apply) (11) 5on73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 20.2201 (d) 20.2203(a) (4) 50.73(a)(2)(iii)
LEVEL (1 0)
Og9 20.2203(a)(1) 50.36(c)(l )(MA) 50.73(a)(2)(iv)(~)
20.2203(a)(2)(i) 50.36(c)(l)(ii)(A) 50.73(a)(2)(v)(A) 20.2203(a)(2)(ii) 50.36(~)(2) 50.73(a)(2)(v)(B)
- - OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii)
I 1 50.73(a)(~)(v)(c)
Specify in Abstract below or in 20.2203(a)(2)(iv)
X 50.73(a)(2)(i)(A)
I 1 50.73@)(2)(v)(D) EXPECTED SUBMISSION ABSTRACT On March 29, 2006, with the plant in Mode 1, left train high pressure safety injection system subcooling control valve CV-3070 failed to stroke open during a preventive maintenance activity, resulting in entry into Technical Specification (TS) LC0 3.5.2.8.1, for the inoperability of one Emergency Core Cooling System (ECCS) train.
On March 31,2006, a shutdown was commenced when it was determined that the 72-hour completion time for restoring CV-3070 to operable status could not be met. On April 1, 2006, the shutdown was completed in accordance with TS LC0 3.5.2.C.1 and 2 required actions.
This event is reportable in accordance with 10 CFR 50.73(a)(2)(i)(A) as the completion of any nuclear plant shutdown required by the plant's Technical Specifications.
The failure of CV-3070 occurred from excessive valve stem interference that resulted from inadequate support of CV-3070's air operator, which occurred as a result of removal of a support hanger. Valve components for CV-3070 were subsequently replaced. A support hanger has been reinstalled to support the valve's air operator.
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FAClLlN NAME (1)
Palisades Nuclear Plant 05000-255 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
EVENT DESCRIPTION
On March 29, 2006, with the plant in Mode 1, left train high pressure safety injection system subcooling control valve CV-3070 [V;BQ] failed to stroke open during a preventive maintenance activity, resulting in entry into Technical Specification (TS) LC0 3.5.2.8.1, for the inoperability of one Emergency Core Cooling System (ECCS) train.
On March 31,2006, a shutdown was commenced when it was determined that the 72-hour completion time for restoring CV-3070 to operable status could not be met. On April 1, 2006, the shutdown was completed in accordance with TS LC0 3.5.2.C.1 and 2 required actions.
This event is reportable in accordance with 10 CFR 50.73(a)(2)(i)(A) as the completion of any nuclear plant shutdown required by the plant's Technical Specifications.
CAUSE OF THE EVENT
During initial investigation, CV-3070 stroked open following minor physical agitation. Subsequent diagnostic testing of CV-3070 showed that valve stem movement was not smooth. Inspection of the valve stem revealed galling along the underside of the stem that coincided with the length of the valve stroke; indicating that the stem was making excessive contact with the valve bonnet backseat surface along the underside of the stem.
CV-3070 is mounted in a vertical pipe section with its air operator oriented horizontally.
Investigation revealed that the end of the valve's air operator was sagging approximately 1.5 inches from horizontal. A search of records revealed that the operator had previously been supported by a hanger that had been removed in 1994.
The failure of CV-3070 was determined to have occurred from excessive valve stem interference that resulted from inadequate support of CV-3070's air operator, following removal of the support hanger.
CORRECTIVE ACTIONS
Valve components for CV-3070 were replaced. A support hanger has been reinstalled to support the valve's air operator.
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
LER NUMBER (6)
PAGE (3 YEAR SEQUENTIAL REVISION NUMBER NUMBER Palisades Nuclear Plant 11 05000-255 11 2006 ' --
003 - '
00 11 rEXT (If more space is required, use additional copies of NRC Form 366A) (17)
SAFETY SIGNIFICANCE
The safety significance of this occurrence is considered minimal. The applicable required actions and associated completion times for one inoperable ECCS train were satisfied in accordance with Technical Specification LC0 3.5.2.
PREVIOUS SIMILAR EVENTS
None