05000249/LER-2014-001, Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing

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Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing
ML15035A062
Person / Time
Site: Dresden Constellation icon.png
Issue date: 01/05/2015
From: Marik S
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR # 15-0002 LER 14-001-00
Download: ML15035A062 (4)


LER-2014-001, Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

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)(iv)(A), System Actuation

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
2492014001R00 - NRC Website

text

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Dresden Nuclear Power Station 6500 North Dresden Road mw Exe ton Generation Morrs, L 60450 815 942 2920 Telephone www.exeloncorp.com 10 CFR 50.73 SVPLTR # 15-0002 January 5, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249

Subject:

Licensee Event Report 249/2014-001-00, Electromatic Relief Valve Failed to Actuate during Surveillance Testing Enclosed is Licensee Event Report 249/2014-001-00, "Electromatic Relief Valve Failed to Actuate during Surveillance Testing." This report describes an event which is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), Any operation or condition which was prohibited by the plant's Technical Specifications.

There are no regulatory commitments contained in this submittal.

Should you have any questions concerning this letter, please contact Mr. Bruce Franzen at (815) 416-2800.

Respectfully, Shane M. Marik Site Vice President Dresden Nuclear Power Station Enclosure: Licensee Event Report 249/2014-001-00 cc:

Regional Administrator - NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station

/I NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 (02-2014)

Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

Reported lessons learned are incorporated into the licensing process and fed back to industry.

Send comments regarding burden estimate to the FOIA, Privacy and Information Collections L

N EV T R P T (Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by LICENSEE EVENT REPO T (LER) intemet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and (See Page 2 for required number of Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. It a means used to impose an information collection does not display a currently valid OMB digits/characters for each block) control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

3. PAGE Dresden Nuclear Power Station, Unit 3 05000249 1 OF 3
4. TITLE Electromatic Relief Valve Failed to Actuate during Surveillance Testing
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED MNH DY YA YER SQETA RE

.YER FACILITY NAME IDOCKET NUMBER MO YEAR YEAR NUMBER NO.

ONTH DAY YEAR FACILITY NAME DOCKET NUMBER 11 06 2014 2014 001

- 00 01 05 15
9. OPERATING MODE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)

El 20.2201(b)

El 20.2203(a)(3)(i)

El 50.73(a)(2)(i)(C)

El 50.73(a)(2)(vii) 5l 20.2201(d)

El 20.2203(a)(3)(ii)

El 50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A)

El 20.2203(a)(1)

El 20.2203(a)(4)

El 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i)

El 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

El 50.73(a)(2)(ix)(A)

10. POWER LEVEL El 20.2203(a)(2)(ii)

El 50.36(c)(1)(ii)(A)

El 50.73(a)(2)(iv)(A)

[E 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

El 50.36(c)(2)

El 50.73(a)(2)(v)(A)

El 73.71 (a)(4)

El 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

El 50.73(a)(2)(v)(B)

El 73.71 (a)(5) 000 El 20.2203(a)(2)(v)

El 50.73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

El OTHER El 20.2203(a)(2)(vi)

Z 50.73(a)(2)(i)(B)

[1 50.73(a)(2)(v)(D)

Specifyin Abstract be3oworin

PLANT AND SYSTEM IDENTIFICATION

Dresden Nuclear Power Station (DNPS), Unit 3, is a General Electric Company Boiling Water Reactor with a licensed maximum power level of 2957 megawatts thermal. The Energy Industry Identification System codes used in the text are identified as [XX].

A.

Plant Conditions Prior to Event:

Unit: 03 Reactor Mode: 5 Event Date: 11-06-2014 Mode Name: Refuel Event Time: 09:12 CST Power Level: 000 percent B.

Description of Event

On November 6, 2014, with the reactor in mode 5, Operations identified that an electromatic actuator failed to actuate during the performance of scheduled surveillance testing. The surveillance involves an operator manually actuating the ERV from the main control room with operators staged in the field. The operators in the field reported an audible click when the manual actuation was initiated. However, when the demand signal was given, the actuator plunger did not move and the valve did not open.

This event is being reported under 10 CFR 50.73(a)(2)(i)(B) "Any operation or condition which was prohibited by the plant's Technical Specifications."

C.

Cause of Event

The cause of this event is under investigation and will be updated in the Supplemental Report.

D.

Safety Analysis

The failure of the 3E ERV to actuate is a non-consequential critical component failure and a Maintenance Rule Functional Failure. The safety significance of the failure will be further investigated when the apparent cause report is complete.

4

E.

Corrective Actions

The failed ERV was replaced with a Hardened design during the Refueling Outage. Additional corrective actions will be updated in the Supplemental Report.

F.

Previous Occurrences

Previous occurrences are being investigated as part of the apparent cause investigation and will be updated in the Supplemental Report.

G.

Component Failure Data

Manufacturer Model S/N Type Dresser Industries 1525VX-3-OS108 BK7082 Relief Valve