05000305/LER-2005-007, Regarding Unanalyzed Condition: Design Deficiency - Component Cooling Water System Inoperable Due to Pump Run Out Conditions

Regarding Unanalyzed Condition: Design Deficiency - Component Cooling Water System Inoperable Due to Pump Run Out Conditions

ML051540040
Person / Time
Site:	Kewaunee
Issue date:	05/27/2005
From:	Gaffney M Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-05-068 LER 05-007-00
Download: ML051540040 (4)

LER-2005-007, Regarding Unanalyzed Condition: Design Deficiency - Component Cooling Water System Inoperable Due to Pump Run Out Conditions

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(viii)(B) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
3052005007R00 - NRC Website

text

MUM NiC Committed to NucdearExcear Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC May 27, 2005 NRC-05-068 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Kewaunee Nuclear Power Plant Docket 50-305 License No. DPR-43 Reportable Occurrence 2005-007-00 In accordance with the requirements of 10 CFR 50.73, "Licensee Event Report System," the enclosed Licensee Event Report (LER) for reportable occurrence 2005-007-00 is being submitted.

This letter contains no new commitments and no revisions to existing commitments.

Michael G !6ffnf/

Site Vice Preside ewaunee Nuclear Power Plant Nuclear Management Company, LLC Enclosure (1) cc:

Administrator, Region l1l, USNRC Project Manager, Kewaunee, USNRC Resident Inspector, Kewaunee, USNRC INPO Records Center sag A N490 Highway 42. Kewaunee, Wisconsin 54216-9511 Telephone: 920.388.2560

ENCLOSURE I LICENSEE EVENT REPORT (LER) 2005-007-00 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 FOlAlPrivacyService Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or byintemet e-(See reverse for required number of mail to lnfocollects=nrc.gov, and to the Desk Officer, Office of Information and Regulatory (See re e

.Affairs, NEOB-10202, (3150-0066). Office of Management and Budget, Washington, DC 20503.

digitslcharacters for each block)

If a means used to impose an Information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the Information collection.

FACILITY NAME (1)

DOCKET NUMBER (2)

PAGE (3)

Kewaunee Nuclear Power Plant 05000305 I

of 2 TITLE (4)

Unanalyzed Condition: Design Deficiency - Component Cooling Water System Inoperable Due to Pump "Run Out" Conditions EVENT DATE (s)

LER NUMBER (6)

[

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8)

S N

IFACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMBER NOMO DAY YEAR 03 28 2005 2005 00 05 27 2005 FACILITY NAME DOCKET NUMBER OPERATING N

THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR,: (Check all that apply) (11)

MODE (9) 20.2201(b) l 20.2203(aX3)(ii)

X 50.73(aX2)(iiXB) l 50.73(a)(2)(ix)(A)

POWER 000 20.2201(d)

T 20.2203(aX4) 1 50.73(aX2)(iii) 50.73(a)(2x)

LEVEL (10) 0 20.2203(aXl)

= 50.36(cXl )(i)(A)

= 50.73(a)(2)(iv)(A) 73.71 (a)(4)

_ 20.2203(aX2)(i)

= 50.36(cXl )(iiXA)

X 50.73(a)(2)(v)(A) 73.71 (a)(5)

- _ 20.2203(aX2)(ii) 50.36(cX2) 50.73(aX2)(v)(B)

OTHER

._ 20.2203(aX2)(iii) 50.46(aX3)(ii) 50.73(a)(2)(v)(C)

Specify In Abstract below or in

_ 20.2203(aX2)(iv) 50.73(aX2)(i)(A) 50.73(a)(2)(v)(D) 20.2203(aX2)(v)

= 50.73(aX2)(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(aX2)(ii)(A) 50.73(a)(2)(viii)(B)

LICENSEE CONTACT FOR THIS LER (12)

PJAI^J T9=1 i punJ;: FJ IkAR;:P1.-4 r

4 Mary Jo Merholz 1

920-388-8277 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) l MANU-REPORTABLE l l MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT FACTURER TO EPIX

CAUSE

SYSTEM COMPONENT FA CTURER TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)

EXPECTED MONTH DAY YEAR YES (If yes, complete EXPECTED SUBMISSION DATE).

X NO D

SUBMISSION

(

l l

ABSTRACT On March 28, 2005 with the plant in Refueling Shutdown Mode, a past operability concern was identified with the plant's Component Cooling Water System. Specifically, on January 23, 2002, plant personnel identified a potential "run out" concern with the Component Cooling Water pumps. The condition assumed Component Cooling Water being aligned to both Residual Heat Removal heat exchangers and both Component Cooling Water pumps running. If a loss of power caused the loss of one Component Cooling Water train and the associated train's isolation valve to the Residual Heat Removal heat exchanger could not be closed, there would be a potential concern with pump 'run out' and pump damage for the Component Cooling Water pump that continued to run. The plant's original design did not preclude the Component Cooling Water pump 'run out" condition. There were no safety significant issues involved with this event. Plant design changes were implemented to alleviate the Component Cooling Water pump 'run out" concern. No further corrective actions are necessary. This report involves a safety system functional failure.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1)

DOCKETNUMBER (2)

LER NUMBER (6)

PAGE (3 Kewaunee Nuclear Power Plant 05000305 R

l SEQUENTIAL R

REVMION 2of 2 2005 007 00 TEXT (if more space is required, use additional copies of NRC Form 366A) (17)

DESCRIPTION

On March 28, 2005 with the plant in Refueling Shutdown Mode, a past operability concern was identified with the plant's Component Cooling Water (CCW) [CC] System. Specifically, on January 23, 2002, plant personnel identified a potential "run out" concern with the CCW pumps [P]. The condition assumed CCW being aligned to both Residual Heat Removal (RHR) heat exchangers [HX] and both CCW pumps running. If a loss of power caused the loss of one CCW train and the associated train's isolation valve to the RHR heat exchanger could not be closed, there would be a potential concern with pump 'run out" and pump damage for the CCW pump that continued to run.

The pump "run-out' concern was determined to be an original plant design issue and was initially resolved by isolating the non-safeguards loads on the CCW system and installing a valve position limiter on a non-critical CCW system flow control valve. Isolation of the non-safeguards loads on the CCW system and the installation of the valve position limiter on a non-critical CCW system flow control valve were completed approximately 49.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> from the time the potential concern was identified. The valve position limiter that was installed was proven effective upon the completion of special operating procedures which verified by testing that a single CCW pump would not experience 'run-out" flow conditions when all CCW safeguards loads, including both trains of RHR heat exchangers were supplied by a single CCW pump.

CAUSE OF THE EVENT

The plant's original design did not preclude the CCW pump 'run out" condition.

EVENT ANALYSIS AND SAFETY SIGNIFICANCE This event is being reported under 1 OCFR50.73(a)(2)(ii)(B), any event or condition that resulted in the plant being in an unanalyzed condition that significantly degraded plant safety, and 1 OCFR50.73(a)(2)(v)(A), any event or condition that could have prevented the fulfillment of the safety function of structures or system that are needed to shut down the reactor and maintain it in a safe shutdown condition.

This event was initially reported on March 28, 2005 as a IOCFR50.72 non-emergency event under criterion (b)(3)(ii)(B), any event or condition that resulted in the plant being in an unanalyzed condition that significantly degraded plant safety (reference Event Notification EN 41539).

This report involves a safety system functional failure.

CORRECTIVE ACTIONS

Plant design changes have been implemented to alleviate the CCW pump "run out" concern. These design changes installed valve travel limiting devices on non-safeguards CCW system flow control air operated valves. These modifications limit total CCW flow to prevent CCW pump "run out" under the specified conditions described in this Licensee Event Report.

PREVIOUS SIMILAR EVENTS

None.