ML18024A868

LER 79-014/01T-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

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: ML18024A866 ML18024A868
References
LER-79-014-01T, LER-79-14-1T, NUDOCS 7906290187
Download: ML18024A868 (8)

Text

4 NEIC F ORM+66 U. S. N AR REGULATORY COMMISSION I7.7Y)

LICENSEE EVENT REPORT

,Q 4>>>> Os~Os CONTROL BLOCK (PI.EASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I

~01 A L B R F 2 Q2 0 0 -' Os 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

~01 7 8 sOURGE LL 60

!QB 61 0 5 0 0 0 DOCKET NUMBER 2 6 68 69 EVENT DATE 74 75 0 6 2 6 REPORT DATE 7 9 80 Q

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 While'n cold shutdown for refuelin local leak rate testin was erformed in accor-

~0 3 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

~0 6 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.

~07

~OB 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCOOE COMPONENT CODE SUBCODE SUBCODE

~OB 7 8 9

~BA 10 Q>i E Qts ~BQss 12 13 V A L V E X Qs ~XQs ~X 20 Q>s 11 18 19 SEQUENTIAL OCCURRENCE

'YPE REPORT REVISION Ql~

LERIRO os sass ACTION FUTURE EVENT YEAR

~79 21 22 EFFECT

+

23 SHUTDOWN

~01 24 REPORT NO.

4 26 27 28 ATTACHMENT CODE 29 NPRb4 30 PRIME COMP.

31 NO.

32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER JQIB ~ZQ10 L~JQ20 ~ZQ" + QJ Q23 QJQ24 ~Q26 z 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 80 FACILITY METHOD OF 7

s STATUS 9

H Qs ~Qss 10 0

Ts POWER 0 0 12 13 OTHER STATUS Q30 NA 44 DISCOVERY

~B 45 Q31 46 Surveillance Testing DISCOVERY DESCRIPTION Q32 80 ACTIVITY CONTENT 7 8

~Z 9 '0 RELEASED OF RELEASE Q33 ~ZQ34 PERSONNEL EXPOSURES NUMBER TYPE 11 NA AMOUNT OF ACTIVITY DESCRIPTION Q39 Q

44 45 NA LOCATION OF RELEASE Q 80

~l7 ~00 0 Qss Z Qss NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 s ~00 0 Qso NA 7 8 9 11 12 80 LOSS OF OR DAMAGE To FACILITY TYPE DESCRIPTION Q43 Z Q42 NA 9 10 80 0

ISSUED

~NQ44 PUBLICITY DESCRIPTION NA

~ V S06290 (87 NRC USE ONLY so 7 8 9 10 68 69 80 o 0

NAME OF PREPARER PHONE: 0

<<V I s

Form BF-17 BF 15.2 6/09/78 .

LER SUPPLEMENTAL INFORMATION 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:

total as found leakage for containment penetrations'as found

'he 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 VALVE VALVE LEAK"RATE '(SOFH) 'PATH LEAK 'RATE I

X-7A 1-14 206.4968 206.4968 1-15 8 X-7B 1-26 454.7919 0. 3248 1-27 9 1-51 24.8211, 24.8211, 1-52 342.5316 X>>205 64 2 X-231 64-29/30 32 33 84-19 X-25 84-8A 600 264.8690 X-205 84-8C 603 75 4 X-25 84-8D 602 77 4 X-9B 3-.568 340.2780 12.4203 71-40 317.9633 3-572 9 12,4203 71-39 8 . 0 69-579 8 3.7809 85-576 9 1.1914 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 1-14 64-21 3-568 71-40 84-19 84-600 1-15 84-602 Valve 1-26 64-32 84-603 No. 1-51 1-52 MFGR Atwood 6 Rockwell Rockwell Atwood & Rockwell WKM Kerotest Morrill Morrill Controls SIZE, 26" 20ll 18tl 24" 6" 2ll 2" TYPE Globe Butterfly Butterfly Swing Check Globe . Check Check PRESS.

CLASS MODEL 20851H 225498 225498 20788H PD420688 RF70-28 .TV-D-9911S-2 DRT MODE OF Air- Air Air Air Air OPER. Oper. Oper. Oper. Oper. Oper.

VLV 1250 psig 125//ANS 125/IANS 1700 psig 1500 psig 150 psig RATING' 575 F 8 380oF NOP 1150 psig 508 508 8 562oF Test Test JGD: JHT 6/22/79'

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