05000255/LER-2008-003, Reactor Protection System and Auxiliary Feedwater System Actuation

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Reactor Protection System and Auxiliary Feedwater System Actuation
ML082030792
Person / Time
Site: Palisades Entergy icon.png
Issue date: 07/21/2008
From: Schwarz C
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 08-003-00
Download: ML082030792 (4)
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LER-2008-003, Reactor Protection System and Auxiliary Feedwater System Actuation
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2552008003R00 - NRC Website
v • d • e

text

Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Tel269 764 2000 July 21, 2008 10 CFR 50.73(a)(Z)(iv)(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 08-003, Reactor Protection Svstem and Auxiliarv Feedwater Svstem Actuation

Dear Sir or Madam:

Licensee Event Report (LER)08-003 is enclosed. The LER describes an automatic actuation of the reactor protection system and the auxiliary feedwater system. The occurrence is reportable in accordance with 10 CFR 50.73(a)(Z)(iv)(A).

Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.

Site vice President Palisades Nuclear Plant Enclosure (1 )

CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC

ENCLOSURE I LER 08- 003 Reactor Protection System and Auxiliary Feedwater System Actuation 2 Pages Follow

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION I APPROVED BY OMB NO. 3150-0104 EXPIRES 813112010 1

I EsZ~m!ed burden per cemse to compiy with this mandatory informtion toMction request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Meported lessons learned are ~ncorporated into the Itcens~w process and fed hack lo I PALISADES NUCLEAR PLANT 1

05000255 I

1 OF 2 m

I LICENSEE EVENT REPORT (LER)

(See reverse for requrred number of digrtslcharacters for each block)

1. FACILIW NAME Reactor Protection System and Auxiliary Feedwater System Actuation
5. EVENT D A E
6. LER NUMBER
7. REPORT D A E
8. OTHER FAClLltlES INVOLVED FACILITY NAME
UChl l NUMRFR DAY YEAR ---

I FACILITY NAME D O C K f l NUMBER

~ndusly. Send comments regard~ng burden est~mate to the Records-uanagement Branch (T-6 E6). U.S. Yucfear Reguiatov Commlmm. Wnshmgton. DC 20555.00131. cr by lntrrnet e-marl to blsl Cnrc gav, anc l o the Desk C'f cer. Offrct. of Infmatrorl and RP ulaiory Affa~rs. NEOS-7MC2 (3I5O-:TMI. Ollice of Manag~vnl aqd Budge!. Waab~nolon. 8~ 20503 I! a rnears uwd to ImposP ~nlorrnatton ccllectrcn dqes nc: d~splay a currert f valrd O W control nurrbcr.

the NRC way not conddct or sfcnsor. and a p r s o n 1s not required tc. respond lo. rl>e rn10rma:~m colleC:m.

2. DOCKET NUMBER I 3. PAGE
9. OPERATTNG MODE q7. TWtS REPORT IS SUBMITTED PURSUANTTO THE REOUIREMENTS OF 10 CFR 5: ( C M k all lhat apply) 1
10. POWER LEVEL 1 00 20.2201(b) ti 20.2203ta)(3) (11 [7 50.73(a)(2)(i)(~)

50.n(a)(2)(vii) 20.2201 (d) 20.2203(a)(3)!ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)( 1 )

20.2203(a)(4)

[7 5O.n(a)(2)(ii)(B) 50,73(a)(Z)(viii)(B) 20.2203(8)(2)(1) 50.36{c){1 )(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(id(A) 20.2203(a)(Z)(ii) 50.36(c)(l)(ii)(A) 50.73(a)(2)(iv)(A) 50,73{a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73!a)(2)(v){A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(li) 50.73(a)(Z)!v)(B) 73.71(a)(5) 20.2203(a)(Z){v)

%.73(a)(Z)(i)(A) 50.73(a)(2)(v)(C)

OTHER Spec11 in Abstract below or in 20.2203 ( a )( 2 )( vi )

13 50.73(a)(2)(i)(B) 17 50.73(a1(2)(v)(~)

NRC &nn 366A Laurie Lahti On May 23, 2008, at 1249 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.752445e-4 months <br />, with the plant in Mode 1 at 100°/~ power, an actuation of the 346 generator negative sequence relay caused an actuation of the 386C coastdown lockout relay.

The 386C relay actuation caused the main generator output breakers in the switchyard to open, causing a turbine trip, which actuated the reactor protective system to trip the reactor. As expected, the auxiliary feedwater system started automatically to recover steam generator level.

12. LICENSEE CONTACT FOR THlS LER FACILITY NAME I TELEPHONE NUMBER (Include Area Code)

(269) 764-2788

CAUSE

X I

The cause of the generator negative sequence relay could not immediately be determined. The relay spuriously failed.

I I I 1

r The relay was replaced and sent to Asea Brown Boveri (ABB) for analysis. The problem could not be reproduced at ABB.

WSTEM EL I

The event is reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A) as an event that resulted in an actuation of both the reactor protection system and the auxiliary feedwater system.

14. SUPPLEMENTAL REPORT EXPECTED YES (ff p, complete 15. EXPECTED SUBMISSION DATE)

NO COMPONENT 87 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines MANU-FACTURER W120 YEAR MONTH DAY REPORTABLE TO EPlX Y

T:uEEt:

DATE

CAUSE

SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX

U.S. NUCLEAR REGULATORY COMMISSION I EVENT DESCRIPTION On May 23, 2008, at 1249 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.752445e-4 months <br />, with the plant in Mode 1 at 100% power, an actuation of the 346 negative sequence generator relay [87;EL] caused an actuation of the 3866 coastdown lockout relay [86;EL]. The 386C relay actuation caused the main generator output breakers [BKR;FK] in the switchyard to open, causing a turbine [TRB;EL] trip, which actuated the reactor protective system [JC] to trip the reactor [RCT;AB]. As expected, the auxiliary feedwater system [BA] startec automatically to recover steam generator [SG;AB] level.

I There were no inoperable structures, systems, or components at the start of this event that contributed to the event. The normal heat sink (main condenser) remained available.

The event is reportable in accordance with 10 CFR 50,73(a)(2)(iv)(A) as an event that resulted in an actuation of both the reactor protection system and the auxiliary feedwater system.

I

CAUSE OF THE EVENT

The cause of the generator negative sequence relay actuation could not immediately be I

determined. The relay spuriously failed.

I CORRECTIVE ACTIONS The relay was replaced and sent to ABB for analysis. The problem could not be reproduced at ABB.

I The relay 346 current transformer circuitry and associated wiring will be inspected for degradation during a future outage.

I SAFETY SlGNiFCANCE The event is considered to be of very low safety significance. All safety systems functioned as expected.

I

PREVIOUS SIMILAR EVENTS

None

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