05000251/LER-1980-006-03, /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

/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
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: 05000251/LER-1980-006, Forwards LER 80-006/03L-0 05000251/LER-1980-006-03, /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
References
LER-80-006-03L-02, LER-80-6-3L-2, NUDOCS 8005130579
Download: ML17339B026 (9)

LER-1980-006, /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

Event date:
Report date:
2511980006R03 - NRC Website

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 Atlantai 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 ID CODE/NAME ACTION:

05 BC O<B < /

COPIES L!TTR ENCL RECIPIENT COPIES ID CODE/NAME L.'TTR ENCL INTERNAL: 01 09 IEE 14 TA/EDO 16 EEB 18 PLANT SYS BR 20 AD PLANT SYS 23 ENGR BR 25 PAR SYS BR 27 OPERA,LiI C BR 29 AUX SYS BR AEOD DOUG MAY TERA JORDAN'

/IE EXTERNAL: 03 LPDR 29 ACRS 1

2 2

1 1

1 1

'1 1

1 1

1 1

1 1

1 1

1 1

10 10 1

1 1

1 1

1 16 16 02 NRC PDR 11 MPA 15 NOVAK/KNIEL 17 AD'OR ENGR.

19 IS C SYS BR 22 REAC SAFT BR 2Q KREGER 26 AD/SITE ANAL'8 ACDENT ANLYS AD/ORP DOR BERLINGERpC, HANAUERiS, 04 NSIC 1

3 3

1' 1

1 1

1 1

1 1

1 1

1 1

1 1

1 3

3 1

1 1

1 INES j ~ 'fggg TOTAL NUMBER OF COPIES REQUIRED ~

LTTR 61 ENCL 61

R 4

t) tt, I

PPZ P

4)

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

FLORIDA POVJER 4 LIGHTCOMPANY 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 4.10.1'UXILIARY FEEDWATER SYSTEM 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.

Program Control (3)

Harold F. Reis, Esquire File:

933.1 TP PEOPLE... SERVING PEOPLE

'0 0

t

NRC FORM SKK P77)'fCENSEE EVENT'REPORT U S NUCI EAR RECULATORY COMMISSION I

I I

t'Ql IPL~s PRINT OR TYPE ALLRKOUIRKO INPORMATIONI IQ I- >>

I I'~IO~Q 9

I 'CKVSKKCOOK'ICSNSK iVUMSKR CON'T

'~o.

'~~L'QE 05 0 00t25 llQ7 0

3 44 't

'QOCKT NUAISKR 43 EVENT O ESCA IPTZON *NO PROS AS I " CONSECUENCES ~lO During performance of XST.'estiFg, the

'"O~Q KVKHTQ*TK 14 75 RKPCIRTOAaK'4

'A'uxiliary 'Feedwater (AFH) pump

~o 3

failed to deliver the flow rate re uired b

TS 4.10.1 to the Unit No.. 4 steam generators..

Pump performance was determined to be satis'factory.

Subse'quent to an evaluat'ion of system performance, the control circuitry

'Z3, of 'the evaluation and events of a similar nature are attached.

0 o-was recalibrated and the system was tested satisfactorily.

A discussion

~oa 7

3 9

1 i

34=

SYSTKM CA45K CAV5$

COMP.

VALVK co as COOK 5LIsc QK ccMSQHKNTcaoK'4$ >>coos SUscaas'09 "S wS L'JS~S LRS aJS 5

9 10 It 11 13

'IS

'9 ZO SKQUKHllAI OCCUR R'KIICK

~ RSPQAT i RKVISIQH ~

LsRIRO KVKNTYs~A RKPQRTNQ caaK TYPK

~

HCL Oia.aiaaar LLI~ ~

~00 6

~m

~03

~L

~

~0 11 IZ Z4 ZS 17 1$

19 34 Zl n

ACTICH PuluRK

KPPKC, SHVTQOWH Al.ACHMKHT HPRQA P'.I INKM>>

CQMPCHKNT TAaCKN ACTICIH CH PLAi'IT SIKTIIQQ

=

HOURS ~22 SUSMatTZO PCRM 549.

SUPpLIKR MANUPAWRK LJsLJs LJs Las ~l Lao Lao I lo 3!

~

40 41 41 44 37 CAUSE OESCRIPTION ANO CORREa IVE ACTIONS Q27 The cause of the low flow was due to either control circuit calibr'ation and/or a flow restriction in valve 4-20-142, 'A'FN pump'ischarge valve to Unit No. 4.

The differential ressure transmitter was recalibrated and.

the system was successfully tested.

Valve 4-20-142 will be inspected 4

3 9

a PACI'UTY~

STATUS

". POWKR OTIIKRSTATuS Cw aa0.LJS ~IS~

a'3 10 I'1 ls 44

• cnVITY caHTKVT RKLKASKO'I RKL~sK AMQUNTQP ACTIVITYQZS

~z.

QZS

~zQZ NA 7

3 9

10 11 44 PKRSONNKI KXPQSURKS HUMSKR 7YPS 0$5CRIPTICN

~0I.0

(

OtQaa ~Z0oa 'iA 7

5 It I'1 13 P SR SQHHKL INJURIES HUAISKR QKscRIPnaHQ>>I a

[Q J Q

I 0IQm NA MKTIIQQQP olscavKBY QIscov~sY QSSFR!PncH

$ 2

~B Q, Surveillance.'i'est2.ng LOCATIONOR RKLKAS\\ QZE NA 30 u

c omi outa e currentl scheduled to start on April 26, 1980.

7 3

9 II I'1 I.CSS QR CR OAMAQK.O FACILITYQia

".YPS QKSCRIPTIQH 9

~ZQA2 3.3 '0 PVSUC:TY

SSUKQ QKSCRIPnaN S 0

LN IQ~

1 l'0'AAIE OF PREPARER NA NA n nman 30 NRC USE ONLY o$

59 30 PNONEI 552-3802

I ib SP 1

l

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'

'C'uxiliary Feedwater'umps to that of the 'A'FW pump indicated the following possible

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 up-'oming outage on Unit No.

4 (currently scheduled to start on April 26, 1980.)

1

0 I

1

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:

900'ize:

6