05000311/LER-2004-008, Unplanned Reactor Trip Due to Main Generator Exciter Brush Failure

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Unplanned Reactor Trip Due to Main Generator Exciter Brush Failure
ML043220383
Person / Time
Site: Salem PSEG icon.png
Issue date: 11/08/2004
From: Fricker C
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N04-0511 LER 04-008-00
Download: ML043220383 (5)
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LER-2004-008, Unplanned Reactor Trip Due to Main Generator Exciter Brush Failure
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(v), Loss of Safety Function
3112004008R00 - NRC Website
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text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 NOV 0 8 2004 LR-NO4-0511 o PSEG NTuclearLLC U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 311 1 04 - 008-00 Salem Generating Station Unit 2 Facility Operating License DPR-75 Docket No. 50-311 This Licensee Event Report entitled "Unplanned Reactor Trip Due to Main Generator Exciter Brush Failure" is being submitted pursuant to the requirements of 1 OCFR 50.73(a)(2)(iv)(A). The attached LER contains no commitments.

Should there be any questions regarding this matter please contact Howard Berrick at 856-339-1862.

Si nere M

Slem Plant Manager Attachment HGB C

Distribution LER File 3.7 95-2168 REV. 7/99

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06130/2007 (6-2004)

, the NRC may dgt/arcenot conduct or sponsor, and a person Is not required to respond to, the digits/characters for each blcOk) 1-__- ; _

3. PAGE Salem Generating Station - Unit 2 0500031 1 OF 4
4. TITLE Unplanned Reactor Trip Due to Main Generator Exciter Brush Failure
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILmES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.

MONTH DAY YEAR

.FACILITY NAME DOCKET NUMBER 09 09 2004 2004 - 008 -

00 1 1 8

2004

9. OPERATING MODE
11. THIS REPORT IS SUBMiTTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 0 20.2201(b) 0 20.2203(aX3XI) 0 50.73(a)(2XiXC) 0 50.73(a)(2Xvii).

1 0 20.2201(d) 0 20.2203(a)(3Xii) 0 50.73(a)(2xii)(A) 0 50.73(a)(2Xvi1i)(A) 0 20.2203(aXl) 0 20.2203(a)(4) 0 50.73(a)(2Xii)(B) 0 50.73(a)(2Xviii)(B) 0l 20.2203(aX2)(i) 0 50.36(cX1Xi)(A) 0 50.73(a)(2Xiii) 0 50.73(a)(2Xix)(A)

10. POWER LEVEL 0

20.2203(aX2)(ii) 0 50.36(c)(1 Xii)(A)

ED 50.73(a)(2Xiv)(A) 0 50.73(a)(2Xx) 0 20.2203(aX2)(iii) 0 50.36(c)(2) 0 50.73(a)(2XvXA) 0 73.71(a)(4) o 20.2203(aX2)(iv) 0 50.46(aX3)(ii) 0 50.73(a)(2XvXB) 0 73.71 (a)(5) 100 D 20.2203(aX2)(v) 0 50.73(aX2)(i)(A) 0 50.73(a)(2)(vXC) 0 OTHER 0 20.2203(aX2)(vi) 0 50.73(aX2)(i)(B)

D 50.73(a)(2)(v)(D)

Specify In Abstract below nr In N~R. Fnrm ')A5AA

12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Coda)

Howard G. Berrick, Senior Licensing Engineer 856-339-1862CAUSE SYSTE OPOET MANU-IREPORTABLE CAS YTMCMOET MANU-REPORTABLE FACTURER TO EPIX

CAUSE

SYSTEM COMPONENT FACTURER TO EPIX E

tM I

I No

14. SUPPLEMENTAL REPORT EXPECTED
15. EXPECTED MONTH DAY YEAR SUBMISSION o YES (If yes, complete 15. E(PECTED SUBMISSION DATE) 0 NO DATE ABSTRACT (Limit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)

On September 9, 2004 at 0106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br /> Salem Unit 2 automatically tripped off line as a result of a Main Turbine Trip which initiated a Reactor Trip. The turbine tripped on Generator Differential and Loss of Field. All control rods fully inserted and all safety related systems were available and functioned as designed. The direct cause of this event was exciter brush/collector flashover. The root causes of this event were that the Generator/Exciter vendors' recommended inspections were not implemented and the lessons learned from a 1993 Hope Creek brush failure were not applied to Salem Unit 2. (Salem Unit 1 is a different Generator/Exciter). Corrective actions taken include replacing the Salem Unit 2 exciter brushes, repair to the collector ring damaged in the brush failure event, incorporation of vendor recommended inspections and guidance into plant procedures. This report is being made in accordance with 1 OCFR50.73(a)(2)(iv)(A), "any event or condition that resulted in manual or automatic actuation of any of the systems listed in paragraph (a)(2)(iv)(B), specifically (B)(1) reactor trip."

NRC FORM 366(6.2004)

PRINTED ON RECYCLED PAPER NRC FORM 366 (6-20w4)

PRINTED ON RECYCLED PAPER

(If more space Is required, use additional copies of (If more space is required, use additional copies of (if more space Is required, use additional copies of NRC Form 366A)

SAFETY CONSEQUENCES AND IMPLICATIONS (contd.)

A review of this event determined that a Safety System Functional Failure (SSFF) as defined in the Nuclear Energy Institute (NEI) 99-02 had not occurred. This event did not impact the ability of safety systems to shutdown the unit or mitigate the consequences of an accident.

CORRECTIVE ACTIONS

1. The Unit 2 Exciter brushes were replaced and damage to the collector ring was repaired.
2. Procedures S2.OP-DL.ZZ-0005 (Q), Salem Unit 2 Secondary Plant Log, and HC.OP-DL.ZZ-0005 (Q), Hope Creek Log 5 Turbine Building Log, will be revised to require daily inspections of the exciters for arcing and degraded conditions, as recommended by the vendor.
3. Operator lesson plans associated with the Main Generator Exciters will be revised to include objectives that cover brush and slip ring inspection criteria, brush arcing and sparking, and the additional lessons learned not directly related to the failure. This training will be provided to Salem and Hope Creek Operators.
4. New weekly and monthly PM tasks will be generated for Salem Unit 2 main and Alterrex brushes (vice the previous every two months PM). The new PMs will include the recommendations from the vendor, will consider recent Operating Experience, and will mirror the main and Alterrex brush inspection guidance that currently exists in the Hope Creek inspection procedure.
5. The scope and schedule of on-going PM Optimization reviews will be reviewed to ensure the PM reviews of critical equipment includes a comparison of the PMs to the vendor recommended PMs and the differences (actual PM less than the vendor recommended PMs) are adequately justified and permanently documented.
6. Salem and Hope Creek system turnover expectations will be reviewed by Engineering for adequacy.

COMMITMENTS

This LER contains no Commitments.

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