ML17263A730

LER 94-008-00:on 940613,B Safety Injection Pump Was Declared Inoperable During Monthly Surveillance Test.Caused by Broken Motor Rotor Bar.B SI Pump Motor Rotor Bars Were Replaced & B SI Pump Motor Was reassembled.W/940713 Ltr

ML17263A730
Person / Time
Site:	Ginna
Issue date:	07/13/1994
From:	Martin J, Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-008, LER-94-8, NUDOCS 9407200011
Download: ML17263A730 (10)

Text

I R.ZuR.za v CCELERATED RIDS PROCESSING)

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9407200011 DOC.DATE: 94/07/13 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna,Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MARTIN,J.T. Rochester Gas & Electric Corp.

MECREDY,R.C. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Document Control Branch (Document Control Desk)

SUBJECT:

LER 94-008-00:on 940613,"B" safety injection pump was declared inoperable during monthly surveillance test. Caused by broken motor rotor bar."B" SI pump motor rotor bars were replaced & "B" SI pump motor was reassembled.W/940713 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR J TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

ENCL ( SIZE:

NOTES:License Exp date i'n accordance with 10CFR2,2.109(9/19/72) . 05000244 RECIPIENT COPXES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL: AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HXCB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRSS/PRPB 2 2 NRR/DSSA/SPLB 1 . 1 NRR DSSA/SRXB 1 1 NRR/PMAS/XRCB-E 1 1 02 1 1 RES/DSIR/EIB 1 1 RGB. ILE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POOREIW 1 1 NUDOCS FULL TXT 1 1

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NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE KVASTE! CONTACT THE DOCUMENT CONTROL Pl-37 (EXT. 504-2083 TO ELIMINATEYOUR NAME FROM DESK, ROOM )

DISTRIBUTIONLISTS FOR DOCUMENTS YOU DON'T NEEDl FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26

ion k f 5kkkk ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.K 14649-0001 ROBERT C. MECREDY TELEPHOkE V<<e Pie>iden< AAEA CODE 716 546 2700 Cinna Nuaeac Rkoduedon July 13, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

LER 94-008, "B" SI Pump Declared Inoperable Due to Broken Motor Rotor Bar, Causes Completion of a Plant Shutdown Required by Technical Specifications R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (i)

(A), which requires a report of, "The completion of any nuclear plant shutdown required by the plant's Technical Specifications", the attached Licensee Event Report LER 94-008 is hereby submitted.

This event has in no way affected the public's health and safety.

Very truly yours, Robert C. Mecredy xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector eZrA Zan&-i~ ~A 94072000ii 9407i3 PDR ADDCK 05000244 PDR

NRC FORH 366 U.S. NUCLEAR REGULATORY COMHISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS.

LICENSEE EVENT REPORT (LER) FORWARD COHMENTS REGARDING BURDEN ESTIHATE TO THE IHFORMATION AND RECORDS HANAGEHENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMHISSION, for required nunber of digits/characters for each block) WASHINGTON, DC 20555 000'I, AND TO THE PAPERWORK (See reverse PROJECT (3150 0104), OFFICE OF REDUCTION MAHAGEMENT AND BUDGET WASHINGTON DC 20503.

FAcILITY HAHE (1) R. E ~ Ginna Nuclear Power Plant DOCKET NUHBER 05000244 (2) PAGE (3) 1 OF 8 TITLE (4) <> Sl Pump Declared Inoperable Due to Broken Motor Rotor Bar, Causes Completion of a Plant Shutdown Required by Technical Specification EVENT DATE 5 LER NUMBER 6 REPORT DATE 7 OTHER FACILITIES INVOLVED 8 SEOUENTIAL REVISIOH FACILITY HAME DOCKET NUHBER HONTH DAY YEAR YEAR MONTH DAY YEAR NUHBER NUMBER 06 13 94 94 --008-- 00 07 13 94 FACILITY NAME DOCKET NUMBER OPERATING THIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR  : Check one or more 11 M(NE (9)

N 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.7'l(b) 20.405(a )(1)(i) 50.36(c) (1) 50.73(a)(2)(v) 73.71(c)

P(NER 097 50.73(a)(2)(vii)

LEVEL (10) 20 '05(a)(1)(ii) 50.36(c)(2) OTHER 20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) (Specify in 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) Abstract below and in Text, 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) NRC Form 366A LICENSEE CONTACT FOR THIS LER 12 HAME John T. St. Martin - Director, Operating Experience TELEPHONE NUMBER (Include Area Code)

(315) 524.4446 CNIPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 REPORTABLE REPORTABLE CAUSE SYSTEH COHPONENT HANUFACTURER CAUSE SYSTEH COMPONENT HANUFACTURER TO NPRDS TO NPRDS BQ MO W120 SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED HONTH DAY YEAR YES SUBH I SS I OH (If yes, conpiete EXPECTED SUBMISSION DATE). X HO DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten tines) (16)

On June 10, 1994, at approximately 1349 EDST, with the plant at approximately 97% steady state power, the "B" safety injection pump was declared inoperable during performance of the monthly surveillance test.

On June 13, 1994, at approximately 1614 EDST, the reactor was placed in the hot shutdown condition to comply with Ginna Technical Specifications for safety injection pump operability requirements.

The underlying cause of the shutdown was inoperability of the "B" safety injection pump, due to a broken motor rotor bar. This event is NUREG-1022 Cause Code (B), "Design, Manufacturing, Construction/Installation."

Corrective action to preclude repetition is outlined in Section V (B).

NRC FORM 366 (5-92)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5.92) EXP'I RES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTIOH REQUEST: 50.0 MRS.

FORNARD COMMENTS REGARDIHG BURDEH ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATIOH AND RECORDS MANAGEMENT BRANCH TEXT CONTXNUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (31/0-0104), OFFICE OF MANAGEMENT AHD BUDGET UASHINGTOH DC 20503.

FACILITY NAME 1 DOCKET NUMBER 2 LER NUMBER 6 PAGE 3 SEQUENTIAL REVISIOH R.E. Ginna Nuclear Power Plant 05000244 94 -- 008-- 00 2 OF 8 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PRE-EVENT PLANT CONDITIONS On June 10, 1994, the plant was at approximately 97% steady state reactor power. Results and Test personnel were performing the

,monthly surveillance test of the safety injection (SI) pumps, in accordance with surveillance test procedure PT-2.1M, "Safety Injection System Monthly Test." Testing of the "A" SX pump had just been completed with satisfactory results, and testing of the "B" SI pump was initiated. At approximately 1349 EDST, the "B" SI pump was started for the monthly test. When the motor was started, a few sparks were noted coming from the motor. (As the motor came up to speed, the sparks stopped.) Control Room operators were immediately notified of the sparking condition, and promptly deenergized the "B" SI pump motor. The "B" SI pump was then declared inoperable.

The declaration of inoperability placed the plant into a Technical Specification (TS) Limiting Condition for Operation (LCO) for TS 3.3.1.4. The action statement of TS 3.3.1.4 allows one SI pump to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If the pump is not operable after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the reactor shall be placed in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and below a reactor coolant system (RCS) temperature of 350 degrees F within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Immediate corrective maintenance was initiated. The "B" SI pump motor was disassembled and inspected. Initial visual inspection by plant and engineering personnel identified that several rotor bars showed crack indications, and one bar appeared to be fully cracked and broken. The rotor was packaged and shipped offsite for repairs.

XI. DESCRIPTION OF EVENT A. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES:

o June 10, 1994, 1349 EDST: The "B" SI pump is declared inoperable.

o June 13, 1994, 1115 EDST: Commenced a reactor shutdown to hot shutdown, and declared an Unusual Event.

NRC FORM 366A (5-92)

NRC FORH 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OHB HO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORHATION COLLECTION REOUEST: 50.0 HRS.

FORWARD COHHENTS REGARDING BURDEN ESTIHATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (HNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF HANAGEHEHT AND BUDGET WASHINGTON DC 20503.

FACILITY HAHE 1 DOCKET NUMBER 2 LER NUHBER 6 PAGE 3 YEAR SEOUEHTIAL REVISIOH R.E. Ginna Nuclear Power Plant 05000244 94 -- 008-- 00 3 OF 8 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) o June 13, 1994, 1614 EDST: The reactor is in the hot shutdown condition, with all control rods inserted and both reactor trip breakers open. Event date and time.

0 June 13, 1994, 1614 EDST: Discovery date and time.

o June 13, 1994, 2157 EDST: The plant is below RCS temperature of 350 degrees F.

o June 13, 1994, 2159 EDST: Unusual Event terminated.

B. EVENT:

On the morning of June 13, 1994, the "B" SI pump motor rotor was at an offsite motor repair facility. Detailed inspections performed at the offsite facility confirmed that one (1) bar was broken, and two (2) other bars were cracked. (This broken bar was the cause of the sparking observed during motor start.)

Repairs were not able to be completed within the next several hours on June 13, nor was a qualified spare rotor located by this time. The Allowable Outage Time (AOT) of TS 3.3.1.4 required the reactor to be in hot shutdown before 1949 EDST on June 13, 1994, and below a RCS temperature of 350 degrees F before 0149 EDST on June 14. Plant management directed that the reactor be shut down and cooled down within the AOT of the TS LCO.

On June 13, 1994, at approximately 1115 EDST, with the reactor at approximately 97so steady state reactor power, the Shift Supervisor declared an Unusual Event, as required by the Ginna Station Nuclear Emergency Response Plan and procedure EPIP-1.0, "Ginna Station Event Evaluation and Classification." This was based on initiating condition "Loss of Engineered Safety Features", for the specific situation of "initiation of a plant shutdown required by Tech Specs due to loss of Engineered Safety Feature for ECCS". At this time, the Shift Supervisor directed the Control Room operators to initiate the shutdown and cooldown to meet the LCO of TS 3.3.1.4.

NRC FORM 366A (5.92)

NRC FORH 366A U.S. NUCLEAR REGULATORY COHHISSIOH APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORMATION COLLECTION REQUEST: 50 ' HRS.

FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORHATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMHISSIONi TEXT CONTINUATION WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTIOH PROJECT (31(0 0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAME 1 DOCKET NUHBER 2 LER NUMBER 6 PAGE 3

'YEAR SEQUENT IAL REVISION R.E. Ginna Nuclear Power Plant 05000244 M

94 -- 008-- 00 4 OF 8 TEXT (If more space is required, use additional copies of NRC Form 366A) (1/)

The shutdown and subsequent cooldown were performed in accordance with normal operating procedures 0-2.1, "Normal Shutdown to Hot Shutdown" and 0-2.2, "Plant Shutdown from Hot Shutdown to Cold Condition." The shutdown proceeded in a normal manner, and the reactor was placed in the hot shutdown condition at approximately 1614 EDST, with all control rods inserted and both reactor trip breakers open. The RCS was cooled down below 350 degrees F at approximately 2157 EDST on June 13, 1994.

With the RCS below a temperature of 350 degrees F, the plant was in a stable condition with no TS LCO action statements in effect for the SI pumps. At. approximately 2159 EDST, the Unusual Event was terminated in accordance with emergency plan implementing procedures.

C. INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT:

The <<B" SI pump was inoperable from approximately 1349 EDST on June 10, 1994, until approximately 1518 EDST on June 15, 1994.

D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:

None E. METHOD OF DISCOVERY:

The completion of the plant shutdown (the event) was preplanned and self-evident. The need for the reactor to be in hot shutdown before 1949 EDST on June 13, 1994, was recognized on June 10. On June 13, it was known that repairs would not be completed within the AOT of TS 3.3.1.4. This was the basis for initiating a reactor shutdown at approximately 1115 EDST on June

13. The completion of the shutdown at approximately 1614 EDST, required by TS, is reportable to the NRC.

NRC FORM 366A (5-92)

NRC FORH 366A U.S. NUCLEAR REGULATORY COHHISSIOH APPROVED BY OHB HO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEH PER RESPONSE TO COHPLY WITH THIS INFORMATION COLLECTION REOUEST: 5D.O NRS.

FORWARD COHHENTS REGARDING BURDEN ESTIHATE TO LICENSEE EVENT REPORT (LER) THE INFORHATION AND RECORDS HANAGEHENT BRANCH TEXT CONTINUATION (HNBB 7714), U.S. NUCLEAR REGULATORY COHHISSION,

'WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140 0104), OFFICE OF HANAGEHEHT AND BUDGET 'WASHIHGTON DC 20503.

FACILITY NAHE 1 DOCKET NUHBER 2 LER NUHBER 6 PAGE 3 YEAR SEOUENTIAL REVISION R.E. Ginna Nuclear Power Plant 05000244 94 -- 008-- 00 5 OF 8 TEXT (If more space is required, use additional copies of HRC Form 366A) (17)

F. OPERATOR ACTION:

The Control Room operators immediately secured the "B" SI pump by deenergizing the pump motor on June 10, and declared the pump inoperable. On June 13, an Unusual Event was declared. The Control Room operators shut, down and cooled down the plant in accordance with normal operating procedures.

The Control Room operators'notified the NRC of the initiation of the reactor shutdown and declaration of the Unusual Event at approximately 1151 EDST on June 13, as required by 10 CFR 50.72 (a) (1) (i) and 50.72 (b) (1) (i) (A). All appropriate agencies were notified of the declaration of the Unusual Event.

The Control Room operators notified the NRC and all appropriate agencies after the termination of the Unusual Event.

G. SAFETY SYSTEM RESPONSES:

None III. CAUSE OF EVENT A. IMMEDIATE CAUSE:

The immediate cause of the reactor shutdown was the need to meet the TS LCO of TS 3.3.1.4 for one SI pump inoperable. The "B" SI pump had been declared inoperable at approximately 1349 EDST on June 10, 1994, and the AOT of TS 3.3.1.4 required that, with one SI pump inoperable, the reactor be placed in hot shutdown before 1949 EDST on June 13, 1994.

B. INTERMEDIATE CAUSE:

intermediate cause of the "B" SI pump being declared N

The inoperable was due to sparks coming from the motor during motor starting.

HRC FORH 366A (5-92)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

FORWARD COMMENTS REGARDING BURDEN ESTIMA'IE TO LZCENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. HUCLEAR REGULATORY COMMISSIOH, TEXT CONTINUATION WASHIHGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140.0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAME 1 DOCKET NUMBER 2 LER NUMBER 6 PAGE 3 YEAR SEQUENTIAL REVISION R.E. Ginna Nuclear Power Plant 05000244 94 -- 008-- 00 6 OF 8 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

C. ROOT CAUSE:

The underlying cause of the sparks coming from the motor of the "B" SZ pump was determined to be a broken motor rotor bar.

The cracking that leads to broken bars is due to fatigue caused by the number of stress cycles imposed on the rotor bars. The principal contributor to stress cycles in the motor rotor (squirrel cage) is the magnetic stresses experienced during motor starting. The frequency of motor starts could significantly reduce the expected service life of the motor rotors. This event is NUREG-1022 Cause Code (B), "Design, Manufacturing, Construction/Znstallationu.

IV. ANALYSIS OF EVENT This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (i) (A), which requires a report of, "The completion of any nuclear plant shutdown required by the plant's Technical Specifications."

An assessment was performed considering both the safety consequences and implications of this event. with the following results and conclusions:

o There were no operational or safety consequences or implications attributed to the "B" SI pump motor rotor sparking because pump motor failure did not occur. Zn addition, the sparking did not continue after the start of the pump. The "B" SI pump motor was immediately deenergized and the pump was declared inoperable.

o The plant continued to operate in accordance with the LCO of TS 3.3.1.4 for the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The cracked rotor bar was not repairable within this 72 hour AOT, so the reactor was placed in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and below a RCS temperature of 350 degrees F within an additional 6 hours per TS. The reactor was operated within the requirements of the TS at all times.

HRC FORM 366A (5-92)

HRC FORH 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTIOH REQUEST: 50.0 HRS.

FORWARD COMHENTS REGARDING BURDEN ESTIHATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (HNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION,

'WASHINGTOH, DC 20555 0001 AND TO THE PAPERWORK REDUCTIOH PROJECT (31/0-0104), OFFICE OF HANAGEHENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAHE 1 DOCKET HUHBER 2 LER NUMBER 6 PAGE 3 SEQUENTIAL REVISION YEAR R.E. Ginna Nuclear Power Plant 05000244 94 -- 008 00 7 OF 8 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

Based on the above, and safety was assured it atcan all be concluded times.

that, the public's health V. CORRECTIVE ACTION A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:

o The "B" SI pump motor rotor bars were replaced at an offsite facility. The "B" SI pump motor was reassembled, tested, and returned to service.

o The issue of motor rotor bar cracking was recently discussed in Westinghouse Technical Bulletin NSD-TB-94-01-RO, "Motor Rotor Bar Cracking", dated 03/17/94. Some Westinghouse Life-line A series and. CSP series motors may exhibit rotor bar cracking. This Westinghouse Technical Bulletin (WTB) had been assessed as part of the Ginna- Operational Assessment. Program, prior to this event. Motors in use at Ginna, of the frame sizes of concern in the WTB, were identified and listed at the time of the assessment. This listconducted of Ginna motors was referred to, and vibration analysis for selected motors. Results of this analysis was indicated that, the "C" SI pump had possible cracked rotor bars. The "C" SI pump motor was disassembled and visually inspected. No visual evidence of rotor bar cracking was identified. The "C" SI pump motor was reassembled, tested, and returned to service.

B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:

The Predictive Maintenance Program is being enhanced to use improved diagnostic vibration analysis methods. Diagnostic testing will be performed periodically to trend for motor inconsistencies, including rotor bar cracking.

NRC FORH 366A (5-92)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5-92) .

EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATIOH COLLECTIOH REQUEST: 50.0 HRS.

FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS HANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, TEXT CONTINUATION WASHINGTON, DC 20555-0001 AHD TO THE PAPERWORK REDUCTION PROJECT (3140 0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAME 1) DOCKET NUMBER 2 LER NUMBER 6 PAGE 3 SEQUENTIAL REVISION YEAR R.E. Ginna Nuclear Power Plant 05000244 94 -- 008 00 8 OF 8 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

VI. ADDITIONAL INFORMATION A. FAILED COMPONENTS:

The failed component is the rotor for the "B" SI pump motor.

This motor is a Model ABDP, frame size 509US, 440 VAC, 3555 RPM, 400 'amp, 350 horsepower motor, manufactured by Westinghouse Electric Corporation.

B. PREVIOUS LERs ON SIMILAR EVENTS:

A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause at Ginna Nuclear Power Plant could be identified.

C. SPECIAL COMMENTS:

None HRC FORM 366A (5-92)