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{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-260 ORG: FOX H S DOCDATE:-03/29l78 TN VALLEY AUTH DATE RCVD: 04l03/78 | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) | ||
NO COPIES RECEIVED | DISTRIBUTION FOR INCOMING MATERIAL 50-260 REC: NRC ORG: FOX H S DOCDATE:- 03/29l78 NRC TN VALLEY AUTH DATE RCVD: 04l03/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED | ||
==SUBJECT:== | ==SUBJECT:== | ||
LTR i ENCL i LICENSEE EVENT REPT (RO 50-260/78-005) | LTR i ENCL i LICENSEE EVENT REPT (RO 50-260/78-005) ON 03/i8/78 CONCERNING UNIDENTIFIED | ||
ON 03/i8/78 CONCERNING UNIDENTIFIED | 'OOLANT LEAKAGE IN DRYWELL FOUND TO EXCEED TECH SPEC 3. 6. C. i... W/ENCL. | ||
'OOLANT LEAKAGE IN DRYWELL FOUND TO EXCEED TECH SPEC 3.6.C.i...W/ENCL.PLANT NAME:BROWNS FERRY | PLANT NAME:BROWNS FERRY UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL: | ||
LTR 45 ENCL 45 SIZE: i P+ | DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002) | ||
FOR ACTION: BR CH AR+> 4 ENCL INTERNAL: REG FILE++M/ENC NRC PDR++W/ENCL MIPC++W/3 ENCL SCHROEDER/IPPOLI TO++M/ENCL HOUSTON44W/ENCL NOVAK/CHECK++W/ENCL I GR MES< 4W/ENCL KNIGHT++W/ENCL BUTLER+4W/ENCL HANAUER44W/ENCL TEDESCO~~W/ENCL E ISENHUT+~W/ENCL BAER++W/ENCL SHA0~4W/ENCL VOLLMER/BUNCH4+W/ENCL KREGER/J., COLLINS++W/ENCL ROSA+~W/ENCL K SEYFRIT/IE++W/ENCL 1 EXTERNAL: LPDR S ATHENS'L+~W/ENCL T I C+4 W/ENCL NSIC++W/ENCL ACRS CA'f B+<W/16 ENCL PER COPIES gOT SUBMITTED REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 780950029 SIZE: i P+ iP+ i P THE END | |||
0 BFRO-50-260/785 Report Number: BFRO-50-260/785 Report Date: March 28, 1978 Occurrence Date: 'arch 18, 1978 Facility Browns Ferry Nuclear Plant Unit 2 Identification of Occurrence Drywell unidentified leakage exceeded Technical Specification value of 5 gpm by 4.5 gpm.Conditions Prior to Occurrence Unit at approximately 90-percent power.Descri tion of Occurrence Drywell unidentified leakage was determined to exceed 5 gpm during surveillance testing.Desi ation of A arent Cause of Occurrence Packing leak from reactor recirculation loop crosstie valve FCV-68-33. | i' 7" NESSEE VALLEY AUTHORIT CHATTANOOGA. TENNESSEE 37401 MAR 39 1978 Nr. James P. O'Railly, Mrector U.S, Nuclear Ra latory Comnission ~ | ||
Anal sis of Occurrence The unit was removed from service, and an inspection of the drywell revealed the leakage from FCV-68-33 as the major contributor to the unidentified leakage.No effects existed upon the public health or safety;redundant systems are not applicable. | 4 | ||
Corrective Action The unit remained shutdown to begin the refuel outage.FCV-68-33 will be repacked with a different type packing.JGD:SGS 3/27/78}} | ~ | ||
Cflt Office of Insp ction and Enforcement r Region II gC. | |||
230 Peachtreo Street, NW., Suite 1217 Atlanta, Geo gia 30303 Deax'fr. 0'illy: | |||
TENNESSEE V AUTHORITY BROHNS PERRY NUCLEAR PLANT UNIT 2 DOCKET NO. 50-260 - PACILITY OPERATINC LICENSE DPR-52 - REPORTABLE OCCURRENCE REPORT BPRO-50-260/785 The enclosed report provides details concerning unidentified coolant leakage in tha dry+all which was found to bo 9.5 gpa and exceeded tha 5 gpm limit of Technical Specification 3.6.C.1. duxing norxml operation. | |||
This report is submitted in accordance ~~ith Browne Perry unit 2 Technical Specifications, Section 6.7.2.B.(2) . | |||
'ary truly youxs, TENNESSEE VALLEY AUTHORITY H. S. Pox Director of Power Production Enclosure cc (Enclosure): | |||
Director (3) | |||
Office of Hanagament Xnformagion and Progran Control U.S. Nuclear Regulatory C ssion Washington, DC 20555 Director (40) | |||
Office of Inspection and Enfor ment. | |||
U.S. Nuclear Regulatory Commiss on Washington, DC 20555 7SOWSOO29 An Equal Opportunity Employer | |||
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~ fB l'9)'LQ) t,Iif ~ I g'p>f f g, g gled | |||
') ff r) ~ )T ~did) Il | |||
) LSC + lf f 'S) I'S) ')S) 'h'd f ')' $ g | |||
~ dfgy il)) Stir )')$ L '~'l",'I " 't&v"d) | |||
.-'.:,l> ",t""")ls..').l | |||
)de SP rh p p 41Pp d ) \ vf, f, V | |||
')9",<"X ', 'I'.'I .h 'N),,) ~'<i' "P )l)i!6"')H " | |||
~ lf if ~ | |||
17 $ P | |||
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'I | |||
)Qf fhl p) jgfl()f)f I f''f )*)fgpl" f ))grfhh'S,d Span,,jfg'f4(d i | |||
,,(Ilkf'<<5 ) I f cf) 3 <> )SW>)r'k>~'9 ~4<)) I f ~ | |||
("C~) '.~-aO>t)'V' | |||
'hf) g()) jA'A 4 'rg<h )Xd,fd)IS 4r VV'') <<hfh .3Q II | |||
~ "444)SI BFA85 10/5/77 NRC FORM 366 LL S. NUCLEAR REGULATORY COMMISSION fl ill E./(HI 0 IT A LICENSEE EVENT REPORT CONTROL OLOCKI Ql (PLEASE PRINT OA TYPE ALLREQUIRED INFOAMATIONf | |||
,6 Pap R 0 0 0 0 0 0 - 0 0 E 4 1 1 1 1QE~QL 9 LICKNSIK CODE 14 15 LICENSE NIJMGKR 26 LICENSE TYPK 40 Sl CAI SS CO'N'T | |||
~ | |||
~O RKPDIIT | |||
~g 0 5 0 0 6 0 8 0 32 8 78 Qo 7 60 61 DOCKET NUMBER IJ4 67 EVENT OATS 14 l5 REPORT DA'IE EVENT DESCIIIPTION AND PR08AOLE CONSEQUENCES Qlo Durin normal o eration unidentified coolant leaka e in the dr ell was I | |||
~o 3 found to be 9.5 m exceedin the 5 limit of Technical S ecification | |||
~o 6 of the reactor was be within 24 hours. There were no effects u on | |||
~OG ublic health or safet redundanc was not a licable. A revious | |||
~8 | |||
~o 7 occurrence was re orted on BFRO-50<<296/7714. (See attached). | |||
~OG 50 7 4 9 | |||
~i8 LJS SYST'M CAUSE CAUSE COMP. VALVf COMPONE'NT CODK | |||
~ | |||
CODE CODE SUSCOOK SUPCOOK SUSCOOK | |||
~O9 9 9 10 'I l LJS 12 12 16 L'JO 'WS 19 20 7 | |||
SEOUENTIAL, OCCURRENCE AEPCRT REVISION | |||
~If ~ ~ | |||
~8 EVENT YEAR RKPOAT NO. COO E TYPE NO. | |||
LfR/RO QEE RE IOII I | |||
~00 84 5 | |||
26 | |||
~W 27 | |||
~01 29 29 | |||
~T 20 Sl | |||
~0 22 21 22 22 ACTION fUTURK EFFECT SHUTOOY/N ATTACHMENT KPR~ PRIME COMP. COMPONENT TAKEN ACTIC'I ON PLANT METHOD HOURS +22 SUBLUTTEO FO>MSU0. SUPPLIER EEEEANUFACTURKR LJSLJS 24 LEES 2'5 LJS 26 Sl 40 LJS LJO LJS 41 42 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 | |||
~10 e occu red f m the cki f fl c ntr 1 valve FCV-68-33 22&nch Darlin Valve Co. No. S150IR)D'ocated on the recirculation loo cross-i | |||
~8~ | |||
on the valve "be erf rmed 4 | |||
7 ~ 9 FACILITY METHOD | |||
'%POWER OTHER S'TATUS QSD OISCOVEAYOI'TATUS DISCOVERY OESCAIPTION Q32 | |||
'E00 LJO 7 9 9 10 12 17 44 LJS 45 46 ACTIVITY C ONTENT 7 | |||
6 9 | |||
~ | |||
RKLEASKD OF RELfASK 9 | |||
Q33 ~gQ3 10 PEASONNfL EXPOSURES I) | |||
AMOUNTOF ACTIVITYQ36 A | |||
41 LOCA'SION OF AELEASE Q3 NUMSER TYPE DESCRIPT)ON Q38 EE 7 9 LOOOOJEQL~JS 9 11 12 12 | |||
~ ERSONNEI. INJURIES EEI 4 | |||
~oo 8 9 | |||
NUMBER 11 OESCRIPTEONQ41 12 N A LOSS OF OA DAMAGE TO FACILITY TYPE DESCRIPTION Q43 9 ~ZQ42 7 6 9 10 O | |||
PUSLI CITY ISSUED DKSCREPTION ~ NAC USE ONLY 7 4 9 I lp 66 69 NAME OF PREPARER PHONE: | |||
*Revision | |||
0 BFRO-50-260/785 Report Number : BFRO-50-260/785 Report Date : March 28, 1978 Occurrence Date: 'arch 18, 1978 Facility Browns Ferry Nuclear Plant Unit 2 Identification of Occurrence Drywell unidentified leakage exceeded Technical Specification value of 5 gpm by 4.5 gpm. | |||
Conditions Prior to Occurrence Unit at approximately 90-percent power. | |||
Descri tion of Occurrence Drywell unidentified leakage was determined to exceed 5 gpm during surveillance testing. | |||
Desi ation of A arent Cause of Occurrence Packing leak from reactor recirculation loop crosstie valve FCV-68-33. | |||
Anal sis of Occurrence The unit was removed from service, and an inspection of the drywell revealed the leakage from FCV-68-33 as the major contributor to the unidentified leakage. No effects existed upon the public health or safety; redundant systems are not applicable. | |||
Corrective Action The unit remained shutdown to begin the refuel outage. FCV-68-33 will be repacked with a different type packing. | |||
JGD:SGS 3/27/78}} |
Latest revision as of 17:46, 2 February 2020
ML18283A995 | |
Person / Time | |
---|---|
Site: | Browns Ferry ![]() |
Issue date: | 03/29/1978 |
From: | Fox H Tennessee Valley Authority |
To: | O'Reilly J NRC/IE, NRC/RGN-II |
References | |
LER 1978-005-00 | |
Download: ML18283A995 (8) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-260 REC: NRC ORG: FOX H S DOCDATE:- 03/29l78 NRC TN VALLEY AUTH DATE RCVD: 04l03/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR i ENCL i LICENSEE EVENT REPT (RO 50-260/78-005) ON 03/i8/78 CONCERNING UNIDENTIFIED
'OOLANT LEAKAGE IN DRYWELL FOUND TO EXCEED TECH SPEC 3. 6. C. i... W/ENCL.
PLANT NAME:BROWNS FERRY UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002)
FOR ACTION: BR CH AR+> 4 ENCL INTERNAL: REG FILE++M/ENC NRC PDR++W/ENCL MIPC++W/3 ENCL SCHROEDER/IPPOLI TO++M/ENCL HOUSTON44W/ENCL NOVAK/CHECK++W/ENCL I GR MES< 4W/ENCL KNIGHT++W/ENCL BUTLER+4W/ENCL HANAUER44W/ENCL TEDESCO~~W/ENCL E ISENHUT+~W/ENCL BAER++W/ENCL SHA0~4W/ENCL VOLLMER/BUNCH4+W/ENCL KREGER/J., COLLINS++W/ENCL ROSA+~W/ENCL K SEYFRIT/IE++W/ENCL 1 EXTERNAL: LPDR S ATHENS'L+~W/ENCL T I C+4 W/ENCL NSIC++W/ENCL ACRS CA'f B+<W/16 ENCL PER COPIES gOT SUBMITTED REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 780950029 SIZE: i P+ iP+ i P THE END
i' 7" NESSEE VALLEY AUTHORIT CHATTANOOGA. TENNESSEE 37401 MAR 39 1978 Nr. James P. O'Railly, Mrector U.S, Nuclear Ra latory Comnission ~
4
~
Cflt Office of Insp ction and Enforcement r Region II gC.
230 Peachtreo Street, NW., Suite 1217 Atlanta, Geo gia 30303 Deax'fr. 0'illy:
TENNESSEE V AUTHORITY BROHNS PERRY NUCLEAR PLANT UNIT 2 DOCKET NO. 50-260 - PACILITY OPERATINC LICENSE DPR-52 - REPORTABLE OCCURRENCE REPORT BPRO-50-260/785 The enclosed report provides details concerning unidentified coolant leakage in tha dry+all which was found to bo 9.5 gpa and exceeded tha 5 gpm limit of Technical Specification 3.6.C.1. duxing norxml operation.
This report is submitted in accordance ~~ith Browne Perry unit 2 Technical Specifications, Section 6.7.2.B.(2) .
'ary truly youxs, TENNESSEE VALLEY AUTHORITY H. S. Pox Director of Power Production Enclosure cc (Enclosure):
Director (3)
Office of Hanagament Xnformagion and Progran Control U.S. Nuclear Regulatory C ssion Washington, DC 20555 Director (40)
Office of Inspection and Enfor ment.
U.S. Nuclear Regulatory Commiss on Washington, DC 20555 7SOWSOO29 An Equal Opportunity Employer
1 ll hf I~ /lt II fl O'Pi h P v'.Vfil ) 4 Sf'l" )) dhh ~ f II f -ff)Idden.y-fq>> y ~I f;, g S,;)
hfdf If i~ 1 - 'f):
.)<i~dr)<<S) g<<-Pg h,",
f: P 1 dd ~,' h Z ~
~
g~ l'f f fdi'I lf I r S, gl lh lj'lh ) R ff)>h l,h
'I' ff I
~ f ); "
l '
'~,4,
~ l (~
II fhfl g,) g gf hf'I I r)hfh LVSIr h
'f $ "g f "V ~> fi" hhSV' gpss,fy ~ ') p~ ,) ~ ve,f.- P )gag )~g f'<<rS: I f rf] g~ J hfj,<<h f S) ) Vl)f I)
J pl'"' fI'O'I, f *] I, f>>p 4, j d Cl jh
~ fB l'9)'LQ) t,Iif ~ I g'p>f f g, g gled
') ff r) ~ )T ~did) Il
) LSC + lf f 'S) I'S) ')S) 'h'd f ')' $ g
~ dfgy il)) Stir )')$ L '~'l",'I " 't&v"d)
.-'.:,l> ",t""")ls..').l
)de SP rh p p 41Pp d ) \ vf, f, V
')9",<"X ', 'I'.'I .h 'N),,) ~'<i' "P )l)i!6"')H "
~ lf if ~
17 $ P
(". > .gg + ad,~ <<
'I
)Qf fhl p) jgfl()f)f I ff )*)fgpl" f ))grfhh'S,d Span,,jfg'f4(d i
,,(Ilkf'<<5 ) I f cf) 3 <> )SW>)r'k>~'9 ~4<)) I f ~
("C~) '.~-aO>t)'V'
'hf) g()) jA'A 4 'rg<h )Xd,fd)IS 4r VV) <<hfh .3Q II
~ "444)SI BFA85 10/5/77 NRC FORM 366 LL S. NUCLEAR REGULATORY COMMISSION fl ill E./(HI 0 IT A LICENSEE EVENT REPORT CONTROL OLOCKI Ql (PLEASE PRINT OA TYPE ALLREQUIRED INFOAMATIONf
,6 Pap R 0 0 0 0 0 0 - 0 0 E 4 1 1 1 1QE~QL 9 LICKNSIK CODE 14 15 LICENSE NIJMGKR 26 LICENSE TYPK 40 Sl CAI SS CO'N'T
~
~O RKPDIIT
~g 0 5 0 0 6 0 8 0 32 8 78 Qo 7 60 61 DOCKET NUMBER IJ4 67 EVENT OATS 14 l5 REPORT DA'IE EVENT DESCIIIPTION AND PR08AOLE CONSEQUENCES Qlo Durin normal o eration unidentified coolant leaka e in the dr ell was I
~o 3 found to be 9.5 m exceedin the 5 limit of Technical S ecification
~o 6 of the reactor was be within 24 hours. There were no effects u on
~OG ublic health or safet redundanc was not a licable. A revious
~8
~o 7 occurrence was re orted on BFRO-50<<296/7714. (See attached).
~OG 50 7 4 9
~i8 LJS SYST'M CAUSE CAUSE COMP. VALVf COMPONE'NT CODK
~
CODE CODE SUSCOOK SUPCOOK SUSCOOK
~O9 9 9 10 'I l LJS 12 12 16 L'JO 'WS 19 20 7
SEOUENTIAL, OCCURRENCE AEPCRT REVISION
~If ~ ~
~8 EVENT YEAR RKPOAT NO. COO E TYPE NO.
LfR/RO QEE RE IOII I
~00 84 5
26
~W 27
~01 29 29
~T 20 Sl
~0 22 21 22 22 ACTION fUTURK EFFECT SHUTOOY/N ATTACHMENT KPR~ PRIME COMP. COMPONENT TAKEN ACTIC'I ON PLANT METHOD HOURS +22 SUBLUTTEO FO>MSU0. SUPPLIER EEEEANUFACTURKR LJSLJS 24 LEES 2'5 LJS 26 Sl 40 LJS LJO LJS 41 42 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27
~10 e occu red f m the cki f fl c ntr 1 valve FCV-68-33 22&nch Darlin Valve Co. No. S150IR)D'ocated on the recirculation loo cross-i
~8~
on the valve "be erf rmed 4
7 ~ 9 FACILITY METHOD
'%POWER OTHER S'TATUS QSD OISCOVEAYOI'TATUS DISCOVERY OESCAIPTION Q32
'E00 LJO 7 9 9 10 12 17 44 LJS 45 46 ACTIVITY C ONTENT 7
6 9
~
RKLEASKD OF RELfASK 9
Q33 ~gQ3 10 PEASONNfL EXPOSURES I)
AMOUNTOF ACTIVITYQ36 A
41 LOCA'SION OF AELEASE Q3 NUMSER TYPE DESCRIPT)ON Q38 EE 7 9 LOOOOJEQL~JS 9 11 12 12
~ ERSONNEI. INJURIES EEI 4
~oo 8 9
NUMBER 11 OESCRIPTEONQ41 12 N A LOSS OF OA DAMAGE TO FACILITY TYPE DESCRIPTION Q43 9 ~ZQ42 7 6 9 10 O
PUSLI CITY ISSUED DKSCREPTION ~ NAC USE ONLY 7 4 9 I lp 66 69 NAME OF PREPARER PHONE:
- Revision
0 BFRO-50-260/785 Report Number : BFRO-50-260/785 Report Date : March 28, 1978 Occurrence Date: 'arch 18, 1978 Facility Browns Ferry Nuclear Plant Unit 2 Identification of Occurrence Drywell unidentified leakage exceeded Technical Specification value of 5 gpm by 4.5 gpm.
Conditions Prior to Occurrence Unit at approximately 90-percent power.
Descri tion of Occurrence Drywell unidentified leakage was determined to exceed 5 gpm during surveillance testing.
Desi ation of A arent Cause of Occurrence Packing leak from reactor recirculation loop crosstie valve FCV-68-33.
Anal sis of Occurrence The unit was removed from service, and an inspection of the drywell revealed the leakage from FCV-68-33 as the major contributor to the unidentified leakage. No effects existed upon the public health or safety; redundant systems are not applicable.
Corrective Action The unit remained shutdown to begin the refuel outage. FCV-68-33 will be repacked with a different type packing.
JGD:SGS 3/27/78