05000261/LER-2009-003, For H.B. Robinson, Unit 2, Regarding Manual Reactor Trip Due to Failure of a Steam Generator Level Module

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For H.B. Robinson, Unit 2, Regarding Manual Reactor Trip Due to Failure of a Steam Generator Level Module
ML100110218
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 01/05/2010
From: Saunders W
Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/09-0114 LER 09-003-00
Download: ML100110218 (5)


LER-2009-003, For H.B. Robinson, Unit 2, Regarding Manual Reactor Trip Due to Failure of a Steam Generator Level Module
Event date:
Report date:
Reporting criterion: 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

10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

10 CFR 50.73(a)(2)
2612009003R00 - NRC Website

text

10 CFR 50.73 Progress Energy Serial: RNP-RA/09-0114 JAN 0 5 2010 Attn: Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 LICENSEE EVENT REPORT NO. 2009-003-00 MANUAL REACTOR TRIP DUE TO FAILURE OF

'A' STEAM GENERATOR LEVEL CONTROL MODULE Ladies and Gentlemen:

The attached Licensee Event Report is submitted in accordance with the requirements of 10 CFR 50.73. Should you have any questions regarding this matter, please contact Mr. C. A. Castell at (843) 857-1626.

Sincerely, W. Scott Saunders Plant General Manager H. B. Robinson Steam Electric Plant, Unit No. 2 WSS/ahv Attachment C:

L. A. Reyes, NRC, Region II T. J. Orf, NRC, NRR NRC Resident Inspector Progress Energy Carolinas, Inc.

Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550

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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES 08131/2010 (9-2007)

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 LICENSEE EVENT REPORT (LER) fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, (See reverse for required number of Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to digits/characters for each block) the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. 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 I respond to, the information collection.

3. PAGE H. B. Robinson Steam Electric Plant, Unit No. 2 05000261 1 OF 4
4. TITLE Manual Reactor Trip Due to Failure of 'A' Steam Generator Level Module
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV NUMBER NO MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 11 06 2009 2009-003 00 01 05 2010 1

05000

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
9. OPERATING MODE [E

20.2201(b)

El 20.2203(a)(3)(i)

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

[l 50.73(a)(2)(vii)

El 20.2201(d)

El 20.2203(a)(3)(ii)

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

F1 50.73(a)(2)(viii)(A) 1 El 20.2203(a)(1)

El 20.2203(a)(4)

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

E]

50.73(a)(2)(viii)(B)

E]

20.2203(a)(2)(i)

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

[E 50.73(a)(2)(iii)

[]

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

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

El 50.36(c)(1)(ii)(A) 0 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)

LJ 73.71(a)(4) 100%

El 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

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

[]

73.71(a)(5)

El 20.2203(a)(2)(v)

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

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

El OTHER Specify in Abstract below or El 20.2203(a)(2)(vi)

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

El 50.73(a)(2)(0v0)(

in could cause a plant transient or loss of control function.

In addition, there are 34 modules where a failure in the power supply could cause the plant to be placed in a V1 trip condition.

The remaining modules are for alarm and indication only.

The safety significance of this event is considered very low.

The plant responded as designed and the operating crew manually tripped the reactor in response to the condition they observed.

The auxiliary feedwater system initiated during the event, as expected.

Therefore, this event posed negligible adverse safety consequences for the public or plant personnel.

IV.

CORRECTIVE ACTIONS

Completed Corrective Actions:

FC-478E summator power supply was replaced with an EnsignTm Power Supply-Revision 4.

Revision 4 does not contain the same capacitors in Revision 3 that caused the premature failure of the power supply.

The channel was tested and restored to normal operation at 1752 hours0.0203 days <br />0.487 hours <br />0.0029 weeks <br />6.66636e-4 months <br /> EDT on November 7, 2009.

Identified and located all HBRSEP, Unit No. 2, modules with EnsignTm Power Supplies-Revision 3 installed.

Placed stock quantities of NUS modules and modules being prepared for installation that contain EnsignTm Power Supplies-Revision 3 "on-hold" to be returned to the vendor for replacement of the power supply.

Planned Corrective Actions

Replace modules in applications that have an EnsignTm Power Supply-Revision 3 where a blown fuse failure could result in a potential transient, loss of control function, or put the plant in a half trip condition.

The module replacements are targeted for completion during the next refueling outage, which is currently scheduled to begin on April 17, 2010.

V. ADDITIONAL INFORMATION

Failed Component Information:

The failed power supply was an Ensigntm Power Supply-Revision 3 contained in a Halliburton summator, Model Number MTH-800-05/05/05/05-07-08.

Previous Similar Events

Licensee Event Reports (LERs) for HBRSEP, Unit No.

2, were reviewed from the past 10 years.

No events were identified that were similar to the event described in this LER.