ML18283A990

LER 1978-010-00 for Browns Ferry Nuclear Plant, Unit 2, Relief Valve on Standby Liquid Control Pump B Opened at 900 Psig (Which Is Lower than Designed Setting of 1425 +/- 75 Psig as Designated by Tech Spec 4.4.A.2.A) During Surveillance Tes

ML18283A990
Person / Time
Site:	Browns Ferry
Issue date:	05/30/1978
From:	Fox H Tennessee Valley Authority
To:	O'Reilly J NRC/IE, NRC/RGN-II
References
LER 1978-010-00
Download: ML18283A990 (6)

Text

y5uC n~go INFORMATION DISTRIBUTION SYSTEM (RIDS)

'EGULATORY

'ISTRIBUTION FOR INCOMING MATERIAL 50-260 REC: OREILLY J P ORG: FOX H S DOCDATE.: 05/30/78 NRC TN,VALLEY AUTH DATE RCVD: 06/07/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT <RO 50-Z60/78-010) ON 05/04/78 CONCERNING DURING SURVEILLANCE TESTINGS RELIEF VALVE ON STANDBY LIQUID CONTROL PUMP "B" OPENDED AT 900 PSIG> VIOLATING TECH SPEC LIMIT OF 4. 4. A. Z. A.

PLANT NAME:BROWNS FERRY UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:P+

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4+~~<4~~<+~4+++~<+

INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: BR CHIEF ORB83 BC++W/4 ENCL INTERNAL: REG FILE++W/E L NRC PDR++W/ENCL MIPC~4W/3 ENCL I 8. C SYSTEMS BR+4W/ENCL EMERGENCY PLAN BR%~W/ENCL NOVAK/CHECK44W/ENCL EEB~~W/ENCL AD FOR ENG+~W/ENCL PLANT SYSTEMS BR~>W/ENCL HANAUER~~W/ENCL AD FOR PLANT SYSTEMSw<W/ENCL AD FOR OPER TECH++W/ENCL REACTOR SAFETY BR4~W/ENCL ENGINEERING BR~~W/ENCL VOLLMER/BUNCH~+W/ENCL KREGER/J. COLLINS++W/ENCL POWER SYS BR++W/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR S ATHENS( AL++W/ENCL T I C+4W/ENCL NSI C++W/ENCL ACRS CAT B~~W/16 ENCL COPIES NOT SUBMITTED PER RE(:ULATORY (:VIDE 10 '

DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781600292 SI2E: ip+1P

%%%%%%4%%%%%%%%4%%4%4%%4%%%4%4%%%%% THE END

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TENNESSEE VALLEY AUTHORIT CHATTANOOGA. TENNESSEE 37401 MAY 3 0 8)II M(llllLIIttIIl'C(PI

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Nr. James P. O'Ref lly, Director U.S, Nuclear Regulatory Commfssfon Office of InspyeV~nr(d Enforcement Regf on II Peachtre6 Street, NtJ ~, Sufte 1217

'30 Atlanta, Geor gfa 30303

Dear Hr,

g'Ref 1'ly:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 2-DOCKET NO. 50-260 - FACILITY OPERATING LICENSE DPR-52 -'EPORTABLE OCCURRENCE REPORT BFRO-50-260/7810 The enclosed report provides details concerning the relief valve on standby lfquid control pump "B" which opened at 900 psig (which fs 'lower than the desfgned settfng of 1425 + 75 psfg as desfgnated by Technical Specification 4.4.A.2.a) during surveillance testing. This report fs submftted fn accordance with Brogans Ferry unit 2 Technical Specfffcatfon 6.7.2.b. (2).

Very tr uly yours, TENNESSEE VALLEY AUTHORITY H. S. Fax Df rector of Po>>zr Productf on Enclosure {3) cc (Encl osure):

Director (3)

Office of Iwtanagatient Information arid Program Control U.S. Nuclear Regulatory Commfssfon Mashfngton, PC 20555 Director {40) f Of fee of Inspection and E fore emen U.S. Nuclear Regulatory Co fssfon t

Vashfngton," DC 20555 An Equal Opportunity Employ<<

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LICENSEE EVENT REPORT ECONTR'GL BLOCK:

I 6 0 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~sl 8 9 A L B LICENSEE CODE R 1 2 14 Qs 15 0 0 - 0 0 0 LICENSE NUMBER 0 0 - 0 0 Qs

'26 26 4 1 1 LICENSE TYPE 1 1 30 Q4~ 67 CAT 68 Qs CON'T 0 5 '3 1 7 8

~01 ~LOB 0 5 0 0 2 6 0 Qj 0 5 0 4 7 8 B Qg 7 8 ~

60 61 DOCKET NUMBER 68 69 EVENT DATE 74 76 REPORT DATE 80 EVENT DFSCRIPTION AND PROBABLE CONSEQUENCES Q10

~o z Durin survei,llance testing, the relief valve on standby liquid control pump "BH opened

~03 at 900 ps ig, which is lower than the des igned setting of 1425 + 75 ps ig as des igna ted by T.S. 4.4.A.2.a. Refueling operations were in progress on the unit; there was no fuel in the reactor vessel; and there were no effects on public health or safety.

Similar events have been previously reported on BFRO-50-296/771, BFRO-50-296/7787 and

~o 7 BFRO"50-296/7713,

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

~OB ~SH Q>> E Qs ~BQ>> V A L V E X Q14 ~XQ15 ~B Qls 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERq)O

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ACTION FUTURE EVENT YEAR

~20 21 22 EFFECT

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23 SHUTDOWN

~01 24 REPORT NO.

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27 HUB 28 ATl'ACHMENT CODE 29 NPROP TYPE U"

30 PRIME COMP.

LJ 31 LJ NO.

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

~EQIB ~g 33 34 QIB ~BQ2o 35

~HO21 36 37 0 0 0 Z 40

~N 03 41 QJO2 42

~O 43 44 C 7 1 o 47 02B CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @27 o The relief valve is a Crosb Valve and Ga e Co. size 1 x 2 st le JKK. The valve's set xes'sure was ad usted ro erl and it was retested and met surveillance testin requirements.

4 80

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7 8 9 FACILITY METHOD OF STATUS '4 POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32

~HQss ~00 O Qss N/A ~BQ31 N/A 7 8 9 10 12 IT 44 45 46 80 ACTIVITY CONTENT RELEASED OF REI.EASE AMOUNT OF ACTIVITY Q N/A LOCATION OF RELEASE Q O33 ~8O34 I 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q3g i ~00 0 jQss 0 Qss N/A 8 11 12 13 80 PERSONNEL INJURIES I 8 9 11 12 80 LOSS OF OR DAMAGE To FACILITY 1'YPE DESCRIPTION Q43 9 ~aQ42 N/A 8 9 10 80 P U 0 L IC ITY NRC USE ONLY ISSUED DESCRIPTION ~48 ss o

0 ~NQ44 s 7 II 9 10 68 69 80 o 0

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