ML17339B026

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LER 80-006/03L-0:on 800407,during Inservice Insp Testing, Auxiliary Feedwater Pump a Failed to Deliver Flow Rate to Unit 4 Steam Generators.Caused by Control Circuit Calibr or Flow Restriction in Valve 4-20-142
ML17339B026
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 05/07/1980
From: Schoppman M
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML17339B027 List:
References
LER-80-006-03L-02, LER-80-6-3L-2, NUDOCS 8005130579
Download: ML17339B026 (9)


Text

REGULATORY FORMATION DISTRIBUTION SY M (BIDS)

ACCESSION NBR:8005130579 DOCeDATE: 80/05/07 NOTARIZED+ NO DOCKET FACIL:50 251 Turkey Point Planti Unit 4i Florida Power and L.ight C 05000251 AUTH NAME

~ AUTHOR AFFILiIAT.ION SCHOPPMANiM ~ AD Flori'da, Power L Light Co ~

RECIP NAME

~ REC'IPIENT AFFII.'IATION Region 2i Atl antai Office of the Director

SUBJECT:

LER 80 006/03L 0:on 800407iduring inservice insp testingi Auxiliary Feedwater Pump A failed to deliver flow rate to Unit 0 steam generators. Caused by control circuit calibr or flow restriction in Valve'-20 142.

DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR ~ ENCL g SIZE! /P3 TITLE: Incident Reports NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME L!TTR ENCL ID CODE/NAME L.'TTR ENCL ACTION: 05 BC O<B < /

INTERNAL: 01 1 02 NRC PDR 1

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09 IEE 2 2 11 MPA 3 3 14 TA/EDO 1 1 15 NOVAK/KNIEL 1' 16 EEB 1 1 17 AD'OR ENGR. 1 1 18 PLANT SYS BR '1 1 19 IS C SYS BR 1 1 20 AD PLANT SYS 1 1 22 REAC SAFT BR 1 1 23 ENGR BR 1 1 2Q KREGER 1 1 25 PAR SYS BR 1 1 26 AD/SITE ANAL'8 1 1 27 OPERA,LiI C BR 1 1 ACDENT ANLYS 1 1 29 AUX SYS BR 1 1 AD/ORP DOR 1 1 AEOD 10 10 BERLINGERpC, 3 3 DOUG MAY TERA "

1 1 HANAUERiS, 1 1 JORDAN' /IE 1 1 EXTERNAL: 03 LPDR 1 1 04 NSIC 1 1 29 ACRS 16 16 INES j ~ 'fggg TOTAL NUMBER OF COPIES REQUIRED ~ LTTR 61 ENCL 61

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P.O. 'BOX 529100, MIAiVII,FL 33152

FLORIDA POVJER 4 LIGHT COMPANY May 7, 1980

- PRN-LI'-80-1 84 Mr.. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement .

U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

REPORTABLE OCCURRENCE,251-80-06 TURKEY POINT UNIT 4.

DATE OF OCCURRENCE: APRIL 7, 1980 TECHNICAL SPECIFICATION FEEDWATER SYSTEM 4.10.1'UXILIARY The attached Licensee E'vent Report is being submitted in accordance with Technical Specification 6.9.2 to provide 30 day notification of the sub-ject occurrence.

Very truly yours, A.. D. Schmidt Vice President

,Power Resources MAS/pa Attachment cc: Director, Office of Inspection and Enforcement (30)

Director, Office of Management Information and.

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Subse'quent to an evaluat'ion of system performance, the control circuitry 0 o- was recalibrated and the system was tested satisfactorily. A discussion 'Z3, of 'the evaluation and events of similar nature are attached.

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REPORTABLE.OCCUPDENCE 251-80-06 LlCENSEE EVENT REPORT PAGE TWO Additional Event Descri tion and Probable Conse uences:

During performance of the monthly ISX test, the 'A'uxiliary Feedwater (AFW) pump did not deliver the required flow of 600 gpm to,Unit No. 4. However, the required flow by the same pump was established within the required time to. Unit No. 3.

Therefore,. the pump performance was believed to be satisfactory. Subsequent to an, evaluation of the possible causes of low flow 'delivered (540 gpm) by the 'A'FW pump, dPT-2401 was, recalibrated. The 'A"'FW pump was then satisfactorily tested to Unit No. 4 by delivering the required'low (600'pm) to the steam generators within the required time .limit (3 minutes)'.

During the event, an operable system flow path was available to Unit No 3 from all 3 AFW pumps and to Unit No.4 from- the 'B'nd 'C'F(l pumps.

Other occurrences attributed to the AFW system were reported as:

AO 250-74-7 LER 250-78-18 LER 250-79-17 LER 250-79-28 LER 250-79-34 LER 250-79-36

.AO 251-73-7'dditional Cause Descri tion and 'Corrective Actions:

The comparison of the delivered flow to Unit No.,4 steam generators by the 'B' Feedwater'umps to that of the 'A'FW pump indicated the following possible 'C'uxiliary causes for low delivered flow (540 gpm) by the 'A'ump:

1. dPT-2401 and dPC-2401 were out of calibration, therefore, the differential pressure between the auxiliary feedwater and steam pressure was not quite enough to over-come the. losses in the long run of piping to Unit No. 4 steam generators..

2., There may be some defect in the internals of valve 4-'20-142 ('A'uxiliary Feedwater Pump discharge to Unit No. 4) that restricts the flow delivered by the

'A'FW pump to Unit No. 4 steam generators.

Both dPT-2401 and dPC-'401 were chec'ked for calibration. No problem was noted with dPC-2401, but'PT-2401 .was found with non-linearity at the middle of the control range which was corrected. The 'A'FW pump was then operated for inspection. The required flow (600 gpm) was, delivered within the required time limit (3 minutes) and the pump performance was satisfactory.,

The possibility of a defect in valve 4-20-142 still exists, because the feedwater regulators needed'o be opened somewhat more than they were opened for the other pumps to deliver the required flow. This problem was discussed with mechanical maintenance and the Plant Nuclear Safety Committee. The valve will be inspected during the outage on Unit No. 4 (currently scheduled to start on April 26, 1980.)

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g 44 REPORTABLE OCCURRENCE 251-80-06 LICENSEE EVENT REPORT PAGE THREE Com onent Data:

dPT-2401 Barton Instrument Co.

Model 225 Valve 4-20-142 Velan Engineering Companies Class:

6 900'ize: