ML17338A693: Difference between revisions
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| issue date = 04/20/1979 | | issue date = 04/20/1979 | ||
| title = LER 79-006/03L-0 on 790322:packing leak-off Observed on Three Valves.Cause Undetermined for Two Valves.Leaking Packing on Third Due to Broken Bellows Seal.Unit in Reeling Shutdown;Repairs Will Be Made Before Return to Power | | title = LER 79-006/03L-0 on 790322:packing leak-off Observed on Three Valves.Cause Undetermined for Two Valves.Leaking Packing on Third Due to Broken Bellows Seal.Unit in Reeling Shutdown;Repairs Will Be Made Before Return to Power | ||
| author name = | | author name = Schoppman M | ||
| author affiliation = FLORIDA POWER & LIGHT CO. | | author affiliation = FLORIDA POWER & LIGHT CO. | ||
| addressee name = | | addressee name = | ||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:iNRC PQRAI 26I3 | {{#Wiki_filter:iNRC PQRAI 26I3 U. S. s4UCI SAR R SCULPTOR y CCMMISSIOii4 l7.77) | ||
LlCEINSEE GVcNT RGI2ORT I Qi iPi SASS PRINT QR TYPc At t RSOUIRcn INIIOR.IzIATION) d | |||
QIO Due to RCS.leakage of 2.S5 gpm, the uni.t was shutdown to permit entry inside the containment. | ~O !2 ! I 00 0 01-10'!0 lo! 0 -! | ||
biological shield-Investigation showed valve 1 packing leak-off to the.RCDT from pressurizer valves.'tlinor leakage from a swagelok,fitting at.the incore detector seal table was also observed.I Following evaluation by'he Plant Nuclear Safety Committee, the unit was~returned.to power and the leak rate was checked each shift to monitor 0 | Ucitlsc:IUMScil I 0! 0 13 C~r 111 1 11 I~IQs 7 UciNsas coda ~ | ||
KN+Su>%3 plu'uaap~~Isc OcSCRIFTION Q2~O'I O 0 Qj Z;no'2 a | oC~'Si i Yss 40 SZ CAi 53 CON'T | ||
~O sau>cs LLOs l 0 0 0 2l 9 1'QT OI3 l2 2 l7 l9 'a 0 4, 2l0,7 !9 Qo 30 at cacxsT "IUMsaR Sa 35 ay ssrowis ts RSP RT OATS 50 Sy GNT OMcCRIPTION ANO PROSsABI.G C NSSCIJSNCc~ QIO 0 Due to RCS.leakage of 2.S5 gpm, the uni.t was shutdown to permit entry 0 IQ inside the containment. biological shield- Investigation showed valve 1 packing leak-off to the. RCDT from pressurizer valves. 'tlinor leakage from a swagelok,fitting at. the incore detector seal table was also observed. | |||
~ZQ2 | Coast I 0 I6 Following evaluation by'he Plant Nuclear Safety Committee, the unit was | ||
The leak rate remained stable at approximately 1.60 gpm through 7iednesday, March 21,'1979.By about 7:00 AH on Thursday,.Harch 22, 1979, the leak rate had increased to 1.85 gpm and by 12:30 PH had increased to 2.85 gpm.At about 1 35 PH, the decision was made to place the reactor in hot shutdown in order to make entry inside the containment biological shield to determine the source of the increased leak rate.The reactor was in hot shutdown at about 2:40 PH.At 4:45 PH, a containment entry was made.The source of the leaks was found to be valve packing leak-offs to the RCDT from pressurizer valves HOV-4-535, HOV-4-536 and PCV-4-455A. | ~ returned. to power and the leak rate was checked each shift to monitor 0 trends in water invento | ||
In addition,. | ~i"'zs S | ||
a minor leak was found from a swagelok fitting at the incore detector seal table for one of the score detector thimbXes that was draining to the containment sump.'ll leaks were evaluated as minor.At about 8:30 AH on Friday, Harch 23, 1979, a second containment entry was made to ensure that all leakage areas had been identified and that the leakage at the incore detector seal table had not increased. | sYs i zM cadi | ||
No additional leaks were found and the leak rate at the incore detector seal table had not increased above the orig-inal leak rate observed.Unit 4 was returned to service at about 2:40 PH on Friday, March 23, 1979.The PNSC agreed with the evaluation that the leakage rate was minor.and recommended | 'AUsa coos CAUss suscaaa 20..>>a¹NTcaos C yp IAl.yr 30 | ||
:the leak rate be checked once per each 8 hour shift in order to monitor trends in the water inventory. | . suacaos suscoas LJHoz LJso g 10 It LJos 12 12 13 L'Jzs lg Lzzs 20 Scau SN TI*I, OCs,itzRF IJC RSPOIET R KVISIOAI 21 22 2$ 23 ig | ||
The PNSC determined operation of Unit 4 with this leakage would not involve any unreviewed safety questions. | =FFacr i.scwucNT ~6'aulsaNczslr A=TION puTURs szsuroaNN PRIucc yr. | ||
LLJ>>Q' AINROA TAS'4 ACTION ON PLANT AI=TIIaa ROURS 4"gsll ~ =0 Foot;I Nua. Sl Pis,-q ixlSLJos LJsz LJos IRO 2Joz I | |||
(l (}} | * zs 24 SS So 40 4I 42 42 41 CAUSc OHCRIPTION ANO CORA-""CTIVS RCTIOz4S of the ackin leak-off could not be determined on two o f'he O22 The cause valves. The leaking packing on the third. vajve was due to a broken bellows seal. The unit is currently in refueling shutdown and repairs will be completed prior to returning to power. | ||
2 I 2 s | |||
a a | |||
g FACIUTY STATUS | |||
~EQzs ACTIVITY CONTassr | |||
~OI 10 RSLSASSO OF Rcl.SASc A Pavlalt 9[3 12 Q NA AMOUSIT OF *CTIsllTY Q~+ | |||
OSO 44 | |||
'uas>CO CF OISC V RY | |||
~A,'-.l 43 Cperator observation OISC I RYO oCRzFTIsssl I.OCATION OF Rcu AS | |||
"'1 Qo 30 Pgg I 3 | |||
~zgs 9 | |||
~zgI I 10 I NA 44 f | |||
45 NA PSRSazAVSI. KN+ Su>%3 plu'uaap ~ ~ Isc ' | |||
OcSCRIFTION Q2 | |||
~O'I O 0 Qj Z;no It IZ | |||
~~o'IA 2 a 12 PcBSONIscl INJI Hzsi slslalacR 033 Rs+TSONQ4 | |||
~QO 0 3 II I '2 | |||
'SS OC OR OAM zii Pa i CIU TY Q+ | |||
aaso:II>>nag a 2 | |||
~ZQ2 '0 Puauclry ssuio asscp>>ttaN Q NA iacRC US- Qssl y 0 fN ~QI 10 sa 30 NAvs o p PRcpRcR N. A. Scho man (305) 552 3802 79050805 t t. | |||
Cg REPORTABLE OCCURRENCE 251-79-6, 0 | |||
LICENSEE EVENT REPORT P AGE TWO Additional Event Descri tion and Probable Conse uences The Plant Nucleary Safety Committee (PNSC) 'reviewed the evaluation of the Unit 4 Reactor Coolant System leakage rate that was in excess of 1 gpm. The sequence of events and the evaluation follows: | |||
At about 7:00 AH on Tuesday, March 20, 1979, the routine calculation of RCS leak rate indicated a leak rate of 1.27 gpm.-. An investigation was initiated to determine the source of this, excess leakage. | |||
By 3:00 PH, March 20, 1979, excess leakage was from: | |||
it was tentatively determined that the source of the (1) Xhe 4A Reactor Coolant Pump number' seal leak-off as there were periodic, standpipe "high. level" alarms, (2) 'valve packing leak-off to the Reactor Coolant Drain Tank (RCDT) as ~ | |||
observed by periodically needing to quench the Reactor Coolant Drain Tank to maintain temperature below 180'F,.and (3) the 4A and 4B charging pump seal pots overflowing. | |||
The leak rate remained stable at approximately 1.60 gpm through 7iednesday, March 21,'1979. | |||
By about 7:00 AH on Thursday,.Harch 22, 1979, the leak rate had increased to 1.85 gpm and by 12:30 PH had increased to 2.85 gpm. At about 1 35 PH, the decision was made to place the reactor in hot shutdown in order to make entry inside the containment biological shield to determine the source of the increased leak rate. | |||
The reactor was in hot shutdown at about 2:40 PH. | |||
At 4:45 PH, a containment entry was made. The source of the leaks was found to be valve packing leak-offs to the RCDT from pressurizer valves HOV-4-535, HOV-4-536 and PCV-4-455A. In addition,. a minor leak was found from a swagelok fitting at the incore detector seal table for one of the score detector thimbXes that was draining to the containment sump.'ll leaks were evaluated as minor. | |||
At about 8:30 AH on Friday, Harch 23, 1979, a second containment entry was made to ensure that all leakage areas had been identified and that the leakage at the incore detector seal table had not increased. No additional leaks were found and the leak rate at the incore detector seal table had not increased above the orig-inal leak rate observed. | |||
Unit 4 was returned to service at about 2:40 PH on Friday, March 23, 1979. | |||
The PNSC agreed with the evaluation that the leakage rate was minor.and recommended | |||
:the leak rate be checked once per each 8 hour shift in order to monitor trends in the water inventory. The PNSC determined operation of Unit 4 with this leakage would not involve any unreviewed safety questions. | |||
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Latest revision as of 11:42, 22 October 2019
| ML17338A693 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/20/1979 |
| From: | Schoppman M FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML17338A692 | List: |
| References | |
| LER-79-006-03L-02, LER-79-6-3L-2, NUDOCS 7905080571 | |
| Download: ML17338A693 (4) | |
Text
iNRC PQRAI 26I3 U. S. s4UCI SAR R SCULPTOR y CCMMISSIOii4 l7.77)
LlCEINSEE GVcNT RGI2ORT I Qi iPi SASS PRINT QR TYPc At t RSOUIRcn INIIOR.IzIATION) d
~O !2 ! I 00 0 01-10'!0 lo! 0 -!
Ucitlsc:IUMScil I 0! 0 13 C~r 111 1 11 I~IQs 7 UciNsas coda ~
oC~'Si i Yss 40 SZ CAi 53 CON'T
~O sau>cs LLOs l 0 0 0 2l 9 1'QT OI3 l2 2 l7 l9 'a 0 4, 2l0,7 !9 Qo 30 at cacxsT "IUMsaR Sa 35 ay ssrowis ts RSP RT OATS 50 Sy GNT OMcCRIPTION ANO PROSsABI.G C NSSCIJSNCc~ QIO 0 Due to RCS.leakage of 2.S5 gpm, the uni.t was shutdown to permit entry 0 IQ inside the containment. biological shield- Investigation showed valve 1 packing leak-off to the. RCDT from pressurizer valves. 'tlinor leakage from a swagelok,fitting at. the incore detector seal table was also observed.
Coast I 0 I6 Following evaluation by'he Plant Nuclear Safety Committee, the unit was
~ returned. to power and the leak rate was checked each shift to monitor 0 trends in water invento
~i"'zs S
sYs i zM cadi
'AUsa coos CAUss suscaaa 20..>>a¹NTcaos C yp IAl.yr 30
. suacaos suscoas LJHoz LJso g 10 It LJos 12 12 13 L'Jzs lg Lzzs 20 Scau SN TI*I, OCs,itzRF IJC RSPOIET R KVISIOAI 21 22 2$ 23 ig
=FFacr i.scwucNT ~6'aulsaNczslr A=TION puTURs szsuroaNN PRIucc yr.
LLJ>>Q' AINROA TAS'4 ACTION ON PLANT AI=TIIaa ROURS 4"gsll ~ =0 Foot;I Nua. Sl Pis,-q ixlSLJos LJsz LJos IRO 2Joz I
- zs 24 SS So 40 4I 42 42 41 CAUSc OHCRIPTION ANO CORA-""CTIVS RCTIOz4S of the ackin leak-off could not be determined on two o f'he O22 The cause valves. The leaking packing on the third. vajve was due to a broken bellows seal. The unit is currently in refueling shutdown and repairs will be completed prior to returning to power.
2 I 2 s
a a
g FACIUTY STATUS
~EQzs ACTIVITY CONTassr
~OI 10 RSLSASSO OF Rcl.SASc A Pavlalt 9[3 12 Q NA AMOUSIT OF *CTIsllTY Q~+
OSO 44
'uas>CO CF OISC V RY
~A,'-.l 43 Cperator observation OISC I RYO oCRzFTIsssl I.OCATION OF Rcu AS
"'1 Qo 30 Pgg I 3
~zgs 9
~zgI I 10 I NA 44 f
45 NA PSRSazAVSI. KN+ Su>%3 plu'uaap ~ ~ Isc '
OcSCRIFTION Q2
~O'I O 0 Qj Z;no It IZ
~~o'IA 2 a 12 PcBSONIscl INJI Hzsi slslalacR 033 Rs+TSONQ4
~QO 0 3 II I '2
'SS OC OR OAM zii Pa i CIU TY Q+
aaso:II>>nag a 2
~ZQ2 '0 Puauclry ssuio asscp>>ttaN Q NA iacRC US- Qssl y 0 fN ~QI 10 sa 30 NAvs o p PRcpRcR N. A. Scho man (305) 552 3802 79050805 t t.
Cg REPORTABLE OCCURRENCE 251-79-6, 0
LICENSEE EVENT REPORT P AGE TWO Additional Event Descri tion and Probable Conse uences The Plant Nucleary Safety Committee (PNSC) 'reviewed the evaluation of the Unit 4 Reactor Coolant System leakage rate that was in excess of 1 gpm. The sequence of events and the evaluation follows:
At about 7:00 AH on Tuesday, March 20, 1979, the routine calculation of RCS leak rate indicated a leak rate of 1.27 gpm.-. An investigation was initiated to determine the source of this, excess leakage.
By 3:00 PH, March 20, 1979, excess leakage was from:
it was tentatively determined that the source of the (1) Xhe 4A Reactor Coolant Pump number' seal leak-off as there were periodic, standpipe "high. level" alarms, (2) 'valve packing leak-off to the Reactor Coolant Drain Tank (RCDT) as ~
observed by periodically needing to quench the Reactor Coolant Drain Tank to maintain temperature below 180'F,.and (3) the 4A and 4B charging pump seal pots overflowing.
The leak rate remained stable at approximately 1.60 gpm through 7iednesday, March 21,'1979.
By about 7:00 AH on Thursday,.Harch 22, 1979, the leak rate had increased to 1.85 gpm and by 12:30 PH had increased to 2.85 gpm. At about 1 35 PH, the decision was made to place the reactor in hot shutdown in order to make entry inside the containment biological shield to determine the source of the increased leak rate.
The reactor was in hot shutdown at about 2:40 PH.
At 4:45 PH, a containment entry was made. The source of the leaks was found to be valve packing leak-offs to the RCDT from pressurizer valves HOV-4-535, HOV-4-536 and PCV-4-455A. In addition,. a minor leak was found from a swagelok fitting at the incore detector seal table for one of the score detector thimbXes that was draining to the containment sump.'ll leaks were evaluated as minor.
At about 8:30 AH on Friday, Harch 23, 1979, a second containment entry was made to ensure that all leakage areas had been identified and that the leakage at the incore detector seal table had not increased. No additional leaks were found and the leak rate at the incore detector seal table had not increased above the orig-inal leak rate observed.
Unit 4 was returned to service at about 2:40 PH on Friday, March 23, 1979.
The PNSC agreed with the evaluation that the leakage rate was minor.and recommended
- the leak rate be checked once per each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift in order to monitor trends in the water inventory. The PNSC determined operation of Unit 4 with this leakage would not involve any unreviewed safety questions.
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