05000260/LER-1979-014-01, /01T-0 on 790526:during Cold Shutdown for Refueling,Local Leak Rate Was Found to Exceed Tech Spec Levels.Caused by Deterioration of Valve Seats in Main Steam, Ventilation, Feedwater & RCIC Sys.Valves Repaired

/01T-0 on 790526:during Cold Shutdown for Refueling,Local Leak Rate Was Found to Exceed Tech Spec Levels.Caused by Deterioration of Valve Seats in Main Steam, Ventilation, Feedwater & RCIC Sys.Valves Repaired

ML18024A868
Person / Time
Site:	Browns Ferry
Issue date:	06/26/1979
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024A867	List: 05000260/LER-1979-014-01, /01T-0 on 790526:during Cold Shutdown for Refueling,Local Leak Rate Was Found to Exceed Tech Spec Levels.Caused by Deterioration of Valve Seats in Main Steam, Ventilation, Feedwater & RCIC Sys.Valves Repaired
References
LER-79-014-01T, LER-79-14-1T, NUDOCS 7906290187
Download: ML18024A868 (8)

LER-1979-014, /01T-0 on 790526:during Cold Shutdown for Refueling,Local Leak Rate Was Found to Exceed Tech Spec Levels.Caused by Deterioration of Valve Seats in Main Steam, Ventilation, Feedwater & RCIC Sys.Valves Repaired

Event date:
Report date:
2601979014R01 - NRC Website

text

4 NEIC F ORM+66 I7.7Y)

LICENSEE EVENT REPORT U. S. N AR REGULATORYCOMMISSION

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8 CON'T

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8 CONTROL BLOCK I

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9 LICENSEE CODE 14 15

,Q (PI.EASE PRINT OR TYPE ALLREQUIRED INFORMATION) 0 LICENSE NUMBER Os 4>>>> Os~Os 25 26 LICENSE TYPE 30 57 CAT 58 sOURGE LL

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5 0

0 0

2 6

0 6

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7 9 Q 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 While'n cold shutdown for refuelin local leak rate testin was erformed in accor-

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dance to technical s ecification 4.7.A.2.

The total leak rate of 5026.5225 SCFH

~0 4

exceeded the allowable 60 er cent of L er 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 707.1 SCFH.

There were no

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si nificant resultin events nor an dan er to health or safet of the ublic. A re-

~06 vious similiar occurrence was re orted on BFRO-50-259 7903.

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80

~OB SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCOOE COMPONENT CODE SUBCODE SUBCODE

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Qts

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A L

V E

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10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERIRO EVENT YEAR REPORT NO.

CODE 'YPE NO.

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os sass

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+

~01 4

21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRb4 PRIME COMP.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER JQIB ~ZQ10 L~JQ20

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QJ Q23 QJQ24

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9 9

9 QB 33 34 35 36

37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o

The excessive total leakage was caused b

deterioration of valve seats on the 'follow-ing systems:

Main steam, ventilation and containment dilution feedwater RCIC. Valve nameplate data is being furnished on a supplement to this report.

The valves were repaired and retested to demonstrate compliance.

4 7

8 9

FACILITY STATUS Ts POWER OTHER STATUS Q30 H

0 0

0 NA 7

8 0

7 8

9 11 12 LOSS OF OR DAMAGETo FACILITYQ43 TYPE

DESCRIPTION

Z Q42 NA 9

10 PUBLICITY ISSUED DESCRIPTION~

~NQ44 NA 9

10 NAME OF PREPARER s

Qs ~Qss 7

9 10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ

~Z Q33

~ZQ34 NA 7

8 9 '0 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

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Qss Z Qss NA 7

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11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 s

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Qso NA 45 NA LOCATION OF RELEASE Q 80 80 80 80 80 VS06290 (87 PHONE:

68 69 80 NRC USE ONLY so 80 o 0

0 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~B Q31 Surveillance Testing 45 46

<<V I s

LER SUPPLEMENTAL INFORMATION Form BF-17 BF 15.2 6/09/78 BFRO 260 /

7914 Technical Specification Involved 3

7 4 Reported Under Technical Specification

6. 7.2.B.4 Date of Occurrence 5 26 79 Time of Occurrence Unit 2

Identification and Descri tion of Occurrence:

'he total as found leakage for containment penetrations'as found to exceed the allowable 60% Lg or 707.1 SCFH.

Total leakage was 5026.5225 SCFH.

Conditions Prior to Occurrence:

Chit 2 shutdown for refueling.

Action specified in the Technical Specification Surveillance Requirements met due to ino erable e ui ment.

Describe.

None A

arent Cause of Occurrence:

There was excessive leakage by valve seating surface.

Anal sis of Occurrence:

None

Corrective Action

The seating surfaces were repaired and retested to demonstrate operability.

(Refer to the attached lists for va1ve data and leakage paths).

Failure Data:

BPRO-50-259-793 Tennessee Valley Authority - Browns Perry Nuclear Plant

I 4

~ EEE0-50-260/7914 VALVE LEAK RATE PATH X-7A X-7B X>>205 VALVE 1-14 1-15 1-26 1-27 9 1-51 1-52 64 2

VALVE LEAK"RATE '(SOFH) 206.4968 8

454.7919 24.8211, 342.5316

'PATH LEAK'RATE I

206.4968

0. 3248 24.8211, X-231 X-25 X-205 X-25 64-29/30 32 33 84-19 84-8A 600 84-8C 603 84-8D 602 264.8690 75 4 77 4

X-9B 3-.568 71-40 3-572 9 71-39 8

69-579 8 85-576 9 340.2780 317.9633 12,4203 0

3.7809 1.1914 12.4203 Not reportable - valve leakage given for information to determine path leak rate.

NOTE:

1-14, 1-15, 1-26, 1-51 and 1-.52 previously reported for exceeding their allowable leakage rates of 11.5 SCFH.

JGD:JHT 6/22/79

~ BFRO-90-260/7914 VALVE DATA Valve No.

1-14 1-15 1-26 1-51 1-52 64-21 64-32 3-568 71-40 84-19 84-600 84-602 84-603 MFGR Atwood 6 Morrill Rockwell Rockwell Atwood Rockwell Morrill WKM Controls Kerotest

SIZE, 26" TYPE Globe 20ll Butterfly 18tl Butterfly 24" Swing Check 6"

Check 2ll Globe 2"

. Check PRESS.

CLASS MODEL 20851H 225498 225498 20788H PD420688 RF70-28 DRT

.TV-D-9911S-2 MODE OF OPER.

Air-Oper.

Air Oper.

Air Oper.

Air Oper.

Air Oper.

VLV 1250 psig 125//ANS RATING' 575 F

125/IANS 1700 psig 1500 psig 150 psig 8 380oF NOP 1150 psig 508 8 562oF Test 508 Test JGD: JHT 6/22/79'

pl

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