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POWER MS""" * November 25, 1998

Docket No. 50-461 10CFR21.21

Document ControlDeskNuclearRegulatory CommissionWashington, D. C. 20555

Subject: 10CFR21 Report 2198-049: Westinghouse DHP CircuitBreaker Refurbished by Nuclear Logistics, Incorporated,Failed to Operate Due to Trip Latch Out-of-Adjustmentandln@rrectly Sized Ratchet Lever Assembly Bushing

Dear Madam or Sir:1

On' September 30,1998, the circuit breaker that had been installed at locationIAP09EE, tripped free during functional checking at Clinton Power Station (CPS). Thebreaker had been removed from location I AP09EE, Drywell Water Chiller IB, and wasbeing prepared for installation in location 1 AP07EF, Drywell Water Chiller I A. Furtherinspection of the breaker found that the trip latch appeared to be out of adjustment andone ratchet lever assembly was an incorrect size. This condition rendered the breakerinoperable in the closing function. The breaker is a Westinghouse Model 50DHP350circuit breaker. The breaker was originally purchased from the Braidwood station andrefurbished by Nuclear Logistics, Incorporated, (NLI) prior to use at CPS.

Condition Report 1-98-10-001 was initiated to track an investigation andresolution of this issue. On October 1,1998, Illinois Powi:r (IP) determined this issuewas potentially importable under the provisions of 10CFR21.

IP is providing the following information in accordance with 10CFR21.21(d)(4).Initial notification of this matter will be provided by facsimile of this letter to the NRC

. s\Operations Center in accordance with 10CFR21.21(d)(3) within two days of the date

the responsible officer signs this letter. (

(i) Walter G. MacFarland, IV, Senior Vice President and Chief Nuclear Officer of 9\

IP, Clinton Power Station, Highway 54, 6 Miles East, Clinton, Illinois, 61727, isinfonning the Nuclear Regulatory Commission of a condition reportable under D,

/the provisions of10CFR, Part 21.

9811300236 981125PDR ADOCK 05000461S PDR _

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11/25/1998 U.S. N:cle:r Reg:latory Commission Operations Ce:ter Eve:I Report P. ige i*

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Power Reactor Event # 35082.................................................... .. .............................................................

|* Site: CLINTON Notification Date / Time: 11/25/1998 14:36 (EST)

' Unit: 1 Region: 3 Event Date iTime: 11/25/1998 11:00 (CST)Reactor Type: [1] GE-6 State:IL Last Modification: 11/25/1998 j

Containment Type: MARK lil

NRC Notified by: RON FRANCE Notifications: MELVYN LEACH R3HQ Ops Officer: LEIGH TROCINE VERN HODGE/ RPM /PCEB NRR

Emergency Class: NON EMERGENCY NIEL DELLA GRECA R1

10 CFR Section: EDWARD MCALPINE R2 ]

|21.21 UNSPECIFIED PARAGRAPH

Unit | Scram Code |RX Crit |Init Power | Initial RX Mode |Curr Power | Current RX Mode1 N No O Cold Shutdown 0 Cold Shutdown

1

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10 CFR PART 21 NOTIFICATION - WESTINGHOUSE DHP CIRCUlT BREAKER REFURBISHED BY NUCLEARLOGISTICS, INCORPORATED, FAILED TO OPERATE DUE TO AN OUT-OF-ADJUSTMENT TRIP LATCH AND i

INCORRECTLY SIZED RATCHET LEVER ASSEMBLY BUSHING

The following text is a portion of a facsimile received from the licensee:

"On September 30,1998, the circuit breaker that had been installed at location 1 AP09EE, tripped free during functionalchecking at Clinton Power Station (CPS). The breaker had been removed from location 1 AP09EE, Drywell Water iChiller 1B, and was being prepared for installation in location 1 AP07EE, Drywell Water Chiller 1 A. Further inspection

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of the breaker found * bat the trip latch appeared to be out of adjustment and [that) one ratchet lever assembly was anincorrect size. This condition rendered the breaker inoperable in the closing function. The breaker is a WestinghouseModel 50DHP350 circuit breaker. The breaker was originally purchased from the Braidwood station and refurbished byNuclear Logistics, incorporated, (NLI) prior to use at CPS."

" Condition Report 1-98-10-001 was initiated to track an investigation and resolution of this issue. On October 1,1998, ,

Illinois Power (IP) determined this issue was potentially reportable under the provisions of 10 CFR [Part) 21."

"lP [provided this) information in accordance with 10 CFR 21.21(d)(4). Initial notification of this matter [wss] providedby facsimile of [a] letter to the NRC Operations Center in accordance with 10 CFR 21.21(d)(3) within 2 days of the datethe responsible officer signs this letter." The letter was signed at approximately 1100 CST on November 25,1998. ,

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The licensee stated that the unit was not in a technical specification limiting condition for operation as a result of this |

issue.

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DRAFT

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' (ii) The basic component involved in this condition is a Westinghouse Model-

50DHP350, 4160-volt, circuit breaker instaHed in a Division 2 Class IE circuit atlocation I AP09EE, supplying non-safety-related Drywell Chiller IB. The breakerwas being prepared for installation in a Division 1 Class IE circuit at locationI AP07EF, supplying non-safety-related Drywell Chiller l A.

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(iii) The circuit breaker was supplied to Clinton Power Station by the Braidwoodstation and was refurbished by NLI prior to installation at CPS.

(iv) Inspection of the circuit breaker identified that the trip latch appeared to be out-of-adjustment and one ratchet lever assembly bushing was an incorrect size. Theincorrectly sized bushing appears to have caused the trip latch adjustment ;

symptom. These deficiencies caused the breaker's ratchet lever assembly tointerfere with the trip linkage as the breaker was closing. The interforace with thetrip linkage caused the circuit breaker to trip free (fail to close). This failuremd== ism was intermittent, and therefore not experienced during previous testingof the circalit breaker at CPS.

Drywell Chillers 1 A and IB do not perform a safety function. The only safety I

function of the circuit breaker in those appucations is to trip open. The " trip open"function of the circuit breaker was not adversely affected by the de6cienciasdiscussed in this report. However, this circuit breaker could have been installed ina number of other applications in the Divisions 1 and 2 safety-related 4160 voltbusses which have a safety function to close. These applications affect p==P

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such as any of the Residual Heat Removal System pumps, the Shutdown ServiceWater System pumps, the Emergency Diesel Generators, the Main Feeds, and theReserve Feeds. If the circuit breaker had been installed in any of thoseapplications, the safety function to close on demand for the applicable equipmentmay not have been met.

IP has concluded that this issue should be reported under the provisions of10CFR21 on the basis that the deviations could have caused a failure ofthebreaker to close during breaker operation and result in a loss ofsafety function forassociated equipment loads.

(v) The apparent trip latch out-of-adjustment and incorrect ratchet lever assemblybushing conditions were identified on September 30,1998 and determined to bepotentially reportable under the provisions of 10CFR21 on October 1,1998.

(vi) A total of three CPS circuit breakers were refurbished by NLL All 3 breakerswere initially rejected by Blinois Power at receipt inspection following thereflubishment by NLI due to various discrepancies The breakers were returned toNLI for repair. The breaker discussed in this report was the only breaker installedat CPS after the NLIrepair.

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* (vii) . The breaker that tripped free has been shipped to another breaker services supplierfor refbibishment. One of the other breakers was returned to CPS from NLI and ispending shipment to the other breaker services supplier for refurbishment. Thethird breaker was returned to CPS from NLI, and CPS personnel inspected and,

| reworked that breaker,

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| A limitation has been imposed on NLI on the CPS Qualified Suppliers List, notallowing rework ofWestmghouse DHP circuit breakers. Inspection criteria forchecking the ratchet lever assembly bushings has been incorporated into the receipt i'

; m=~+Jon checidists for new and refurbished DHP model circuit breakers. i

(viii) Additional information about circuit breaker refurbishment performed by NLI may ;

be obtained by reviewing NUREG 0040, "I ic-m Contractor and Vendor i

Inspection Status Report," Volume 22, Number 2, dated April-June 1998.||

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Additional information about this issue may be obtained by contactmg {R. A. Philipps, Plant Fagia--mg, at (217) 935-8881, extension 3464.

Sincerely yours,'

RO, b3

| Walter G. MacFarland,IV| Senior Vice President and !

ChiefNuclear Officer I

RSF/krk

cc: NRC Clinton Licensing Project Manager i

L NRC Resident Office, V-690| Regional Administrator, Region HI, USNRC |

Illinois Department ofNuclear Safety |

INPO Records CenterNuclear Logistics, Incorporated

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