ML20138E937
Text
_ - _ -.... - -.
-- +. -.
oV
~
February 22, 1996 50-334 l?-
- g I d MEMDRANDUM T0
Ellis W. Merschoff, Director i}l Division of Reactor Projects 4
1 Region II I
I 4
FROM:
Charles E. Rossi, Director
>j Safety Programs Division Office for Analysis and Evaluation j j of Operational Data
}l
SUBJECT:
AEOD INPUT FOR THE VISIT OF CHAIRMAN JACKSON TO ST. LUCIE
- 'i ON APRIL 2, 1996 1
.-3 q
Per your staff's request, attached is the AEOD input to the briefing package l
Jj for Chairman Jackson's visit to St. Lucie on April 2, 1996.
i!
Our input consists of a summary analysis of the recent operational experience
'i at St. Lucie Units I and 2.
It is based on several data sources, including
.1 Emergency Notification Reports, Licensee Event Reports, and AE00 Performance i
lj Indicator data.
li
Attachment:
As sta.ted
.l CONTACT: Robert A. Spence, AE00/SPD/RAB i1 (301) 415-6346 1'j cc w/att:
'i J. Mitchell, EDO R. Prevatte Senior Resident Inspector.
K. Landis, RII J. Norris, NRR
,j s
Distribution:
i :j:
Central File
!j RAB R/F
- j SPD R/F 4 1 EJordan
)
ii Dross FCongel DHickman KRag11n, TTD PBaranowsky LSoffer, EDO ji 3-tW h M lly i
hboM7 0/37 j
DOCUMENT NAME:C:\\WP51\\WPDOCS\\COMVISIT\\STLUCIE. RAS i
To resehe a copy at thle document, Indicate in the bez: T's Copy adhout ^^
" T
- Copy adh N"""
l w u em ad OFFICE RAB C
RAB f3 C:RAB f '
M D:SPD A/
'l; NAME RASpence:nek R85 RLLloyd (/W JRosenthal Cross W J DATE 02/2 0/96 02 & /96 I 02/J4/96 02/E./96 t
NSC F:LE CENTER COPY
l l>
e*
V 1
s 4
6 y
+i 4
I i:
..)i
SUMMARY
OF RECENT OPERATIONAL EXPERIENCE i
- l AT ST. LUCIE UNITS 1 AND 2 1 3 FOR CHAIRMAN JACKSON'S VISIT ON APRIL 2,19%
s
' aj l
4 a
1 2
3 i
+
I.
t.
l '4, i
i 3
c4 1
I 1
i,
- ;i
,g i
i 1
h i
1
,i r.J..
d J
l,j j i i
1
.m Il 1
i d
i Safety Programs Division Office for Analysis and Evaluation
]
of Operational Data l 4 1
a j
[ffAf*bM
\\
!l 1
4
s
!j a r
l9 1:
I
)
!1
\\:
4l
SUMMARY
OF RECENT OPERATIONAL EXPERIENCE l1 AT ST. LUCIE UNITS 1 AND 2 i
I L
OVERVIEW i
1
- J, The review period began January 1,1995, and included reports that AEOD processed through January 31,1996. During this period, the NRC did not classify any St. Lucie events as
!1]
j NUREG-0090 Abnormal Occurrences or Appendix C items ("Other Events ofInterest"). Of l1 the events reported in the Licensee Event Reports (LERs) and the emergency notification
!{
system (ENS) submitted during the review period, six LERs were found to be important using
[
the AEOD screening process 5
i 4
IL OPERATIONAL DATA 1
h review penod began on January 1,1995, and included those reports processed through j
Jennary 31,1996. We reviewed LERs 335/95-001-00 through 335/95-010-00 on Unit I and LERs 389/95-001-00 through 389/95-005-00 on Unit 2.
j l
Unit 1 j
LER 335/95 404, " Hurricane Erin at St. Lucie" mported a controlled shutdown of both units l'
in accordance with the plants' Hurricane Preparadaman Procedures on August 1,1995. On i
August 2,1995, operators found that a reactor coolant pump lower seal stage had failed and
{
attempted to restage the failed seal, even though that procedure had not been previously perfonned while reactor molant system (RCS) temperature was above 200 *F.
' Ibis caused the middle and upper seal stages to fail and result in a 2 spm idaatified RCS leak to the
- j..
==*aiammane Dunng the cooldown and depressurization of the RCS, a valid main steam l
isolation signal was received due to an operator's failure to block the signal, as required by k
Procedure.
a LER 335/95-405-00, " Pressurizer Power Operated Relief Valve (PORV) Inoperable due to i
Personnel Error," reported a plant cooldown and depressurization on August 9,1995 to comply with eachnical specifications after the operators could not confirm that the PORVs were opening as expected during stroke testing Later dinamaamhly of the PORVs revealed that the main disc guide had been installed iwdy by contractor =minemaanm personnel.
-j The paae-==iatanance procedure had been inadequate in that it did not test the main valve's 4
ability to stroke when the pilot ar*==*ad. The inservice testing had been inadequate in 'diat it did not confirm the test results with all available plant parameters, but relied on acmw.ic response in the PORV tailpipe, which could give false positive test results.
Ia LER 335/95-006-00, "I.oss of Reactor Coolant Inventory '!hrough a Shutdown Cooling Relief i
Valve due to Lack of Design Margin," reported a lifting of a thermal relief valve in the common low pressure safety injection discharge pip'mg that would not resent on August 10, 1
4 l
1
ii
- y
, A,
}
- q 1995. A low pressure safety injection pump was started to initiate flow for shutdown cooling li operation during the cooldown to investigate the PORV inoperability described above. A thermal relief valve lifted dunng the pump start and did not resent About 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> later, after l'
approrimmealy 4000 gallons of reactor coolant accumulated in the pipe tunnel, the pump was i3 shutdown. The root cause of the event was lack of design margin between the relief valve j
hfting and resenting setpoints and normal system pressure Corrective actions included
!1 increasing the lift setpoint and minimum blowdown required, replacement of the thermal relief
!l valve, and evaluation of the available design margin for 114 other safety-related relief valves on both units. Seventeen of these valves required additional analysis and actions to increase j
the margm between system operating pressure and the resent setpoints. A Severity Level IV l
violation was issued because the relief valve setpoint and blowdown condition was identified j,
on February 20, March 2, and March 10,1995, but did not receive prompt corrective actions t2 LER 335/95-010-00, " Manual Reactor Trip Due to Low Steam Generator Water Level Caused by Main Feedwater Ragal=*iag Valve Closure," reported a manual trip from 100 percent power due to decreasing water level in one of the steam generators that occurred on November 16,1995. A degraded 24 V dc power supply, coupled with a voltage drop j ;
associated with the start of two fire pumps during a surveillance test, resulted in a voltage loss to the feedwater controller, which caused the partial closure of the main feedwater regulating
!j valve supplying feedwater to the steam generator "Ihe voltage drop from the fire pumps Iq starting also caused several control room annunciators to alarm spuriously. The licensee replaced the main feedwater regulating controller power supply; tested similar unit 2 power j
siipphes; and evaluated a preventative maintenance anhancamane, a plant modificaten to provide a normal source of power to the feedwater regulating system from a vital 120 V i
l3 electrical bus, and the cause of the spunous control room alarms.
l j
Unit 2
\\ii, LER 389/95-004-00, " Reactor Coolant System Instrument Nozzle Leakage t'anead by Pnmary Water Stress Corrosion Cracking," reported boric acid buildup on an instrument nozzle j'
indicative of reactor coolant system leakage that was found during a visual check in a lj refueling outage Isotopic analysis of the residue demonstrated that no active leakage had occurred for a significant amount of time. The crack was most probably caused by primary i
water stress corrosion cracking of the alloy 600 material, which had shown susceptibility to i!
such cracking in similar events at San Onofre, Calvert Cliffs, ar.d St. Lucie 'Ibe defective instrument nozzle and other RCS nozzles having the same best number were replaced prior to unit startup i
1 LER 389/95-005 00, "2A Emergency Diesel Generator Relay Socket Failures Due to High 4
j!
Cycle Fatigue," reported that a diesel generator local start failure on November 3,1995 was J
caused by a shutdown relay socket solder joint crack. The licensee tested all relays in place i{
and found and removed two additional suspect relay sockets After remote load control was j
lost at 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test run, the licensee shut down the diesel generator and j
developed a procedure to inspect the remaining relay sockets. Laboratory testing attributed 2
a.
/
ri *.
il' j
the degradation of the relay sockets to high cycle fatigue from vibration la the diesel y
generator rooms The licensee replaced all relay sockets on all diesel guerators, load tested i
both unit 2 diesels for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and made a Nuclear Networt notification on the problem.
III. PERFORMANCE INDICATOR DATA The most recent approved Performance Indicator information for St. Lucie Units I and 2 are attached J
i
)
i i
a Y
I i
- i 3
- -. yu m m, g.: ~. -
1:-
i l ld j
w
- i ST LUCIE 1 iwusano a
opermen mum industry Avg. Trond shutdown 155555 s2 4 to eso Quarktf DW f
NotshownUdngop.Cym egnB q
l i
I I
I I I
I I
i I
I i
I l
I I
n r
n
,,,,I
,I I,,,
,I se,
g,i
,i i,,,
i ;
,I,
j se,
g, g,
g g,
4 g
g j
3-3 g
2-2-
M s,_ q.,
... m., n.,
s a.m.-n e==
r s=-e rea-o.
2, j ts.
ats.
l 31A-gJ 2-03-1-
8 g
M m.f e
i
.f ess _nSt nos as.f us
.f ma _nSt oss use y
y a w,- = re-asa m e w ressed cesse meanfut seescemensuescessesinuse 80 1
3.-
1..
1l 4
j..
g..
b 98 t* g 0
,,,,,,,,,,,,,,, g 8
US.f
.f b.tJs oper
- e. comer Pur CeGeogue mmenSem angessee g
'a-l ltoo.
G m
g o-gg,,.
.-h
,,,, a e
....i.
r..
.i[
i !
!l ST. LUCIE 1 to.ene -se j
Pwr Gmur Combuston Engineering w/o CPC teedhan m jI G2-4 m 95-3 Trende and Devistone
- j Devistons From Plant Peer Group Set-Trond Median i
i Short Term Lon0 Term OPEftAT1ONS ("=P: "'r.m; startup)
Automenc Scrams m Cruical 0
-0.56 l
Safety Systern ha% '
O.90 l
-0.36 l
! :l l
Signincent Events -
0 0
il
~
j j Safety System Failures -
o 0.22 I !).
Cause Codes (All LERs) f
& Adushemuseusammene Peumamme -
0 E 0A5
- }
kusammesosasseurspises - I
,1 4.90
] 0.22
{
t cour Puummmes oreuse -
l l 4.84 0
i
& ensemanummes piumenes - 4As l0.14
'j
+
t passamme -
0.25 E Om j
l{
1 MhmeAmmmmes -
0 4.18 [
i
- i j
Sasetysystem 0.96
-0.s7 i
SignlAcant Events -
o o
a Safety System Failures -
122 4.01 j1 Cause Codes (AN LERs)
] 0.11 0m [
& am me==
om== p.unemm. -
et usemens opusser absure -
0 O
4 l 3
]0.15 4.14 [
a caer Passamme m -
l4
]Om 42 [
& lamaammmase psenemme -
f E 02 0
a Pounemme -
j' t seensammanus -
0 0
N OUTAGES j1l Forced Outage Rate *
-E83
-0.10 j
Esguipment Forced Outageef *
-2.46
-as2 j
i tooo commerosas crescas Hours i
1D 4'S O'D O'S 1D 1D 4'B O'D O'S 1D 1
Performance indem PerformeneInsiest j
- eensosemamesuropsuemmesoyeem I
4
i
?l 6 1
i.
Id ST. LUCIE 1 y
i FI ETENTS FOR 94-4
'j SSF 10/23/M LEmp 335M006 50.7a#: 27im
,a MS NIST: CSDITION EXISTED IN ALL NBES UP TO 100E poler StaCE 1978 i
ORolF CONTAlleWIT AW CONTAIWWIT ISOLATION WOUP
! j)-
STSTM : REACTOR W NTAlm erf IUILLING A
DESC
- A Male ERAW COULS HAVE ALLOIS CIISBS TRAIN PREdSR12ATION OF AN IDLE CMTAlWENT SM'AT MSP.
TNIS Ceuts IIAW MalLTED IN A RELIEF WALW LIFTIIIS AB CWITAIWWIT 55F IINBffWY LOOS ft flE a
j ABA(ILIART SUILDIIIG IN ENCESS OF DESIGI LINITS.
i SCEAM 10/as/96 LEnf 335M 007 50.73#: 27954 Ma MIST: PCIst GPERAficus AT 100E
!?
MSC A REACTER TRIP POLLERS A IIAIN TLABIE TRIP. TNIS OCQEM lAWI A FAULTD SWITCII TAAD POTEIITIAL TRANSNWER CAMIED A II41N MIERATM LOCmff.
4j SSR 11/22/96 LEnf 335M00F 50.729: asete mm BIST: 4xna sinffsmAl M9C
illTN ASDITICIIAL LOADIts Peel TIE SIAS Cause Tile gut IREAIER TO OPBl.
3 SS&
11/22/M Lanf 335M 00F 50.739: 200A0 M a NIST: COLD staffsmal DESC
- AN SIAS """m lAWB TUD OF PRR PRESERIZER PESOURE TRANENITTERS ORIFTB N!all DE TO ENTRAPPED llV9ADEll. TIIE CMARSleG MSFS lERE SEOW BEPM TE LTtr NTPOINT las MAcam.
881 11/36/96 Leaf 335M010 50.729: 20080 Plat NIST: COLD supTBG E MSC
- All IRADWRTENT SAPETT IuJECTICII ACTUAflou SISIAL OCaman RAtlus AEACTOR PROTECT!WE AfD EIIGIIIMBAD SAFESIANS SYSTM TESTIIIG lAWB A PREsmRINR PRESSAE BISTABLE TRIPPO. TIIE CAME tins A DEFICINT j
j FI ETENTS FOR 95-1 7j SSA 02/14/95 LEIf 3B95001 50.73f: 2360s Ma utst Past OPRATIGIB AT 180E BESC nellLE MSTORINE A SAPETT EUS TO A WINEL LIlmiP POLLOlfles MLAT N, TM EMS 6818 j
DWWI23. 73 mammerf DIEEL STARTM AS LGABS INTO TE ass.
FI ETENTS FOR 95-2 NOME FI ETENTS FOR 95-3 i
S C E A M OT/08/95 L a f 3 B95005 50.73f: ageN FtR BIST: Pam GPWAflaus AT 198E DESC THE MALTOR TRIPPS el NION PEEEERI2EE Pe8emm8 lABI TIE NAls TLABIIE GDUMUDE AfD luTEmmPT URLUES LENT CLOW StAING TESTINE. TNIS EVENT las CAMW ST All EpWATOR 911T7158 A TEST Pactam j
STup.
SSF-08/9p/95 Laf Imp 50g5 50.73#: 29175 i
Pla utST: castflou EXISTS Im ALL m eet UP 70 100E PGElt SINCE 19 M Map : SAFETY M MLIEF 11hLVER Map MACTER 030LANT SYSTWI SYSTWI :
TE PmER OPEATB MLIEF WALUES M PRES IIINRIRAALE BimilIS TESTIWE. TIE 11415 CISC SIIDES W DRec i
luBTALLS It0MLY Btstles TM 19M MMELIES ERffM.
Jj SSF M/14/95 L W IW95N 6 50.7N:
Ma MIST: EWeNT occuuma la uma servens 7
GASF : MSIBWL MT M 3T5735 mmP M BaglRL M T M SYSTWI SYSTWI : ESTE 194155 0F WBIO4IhL MAT WWURL M M laupmAALE AB A MER.T OF A PAILS trEN EMCTION i
I BESC MLIEF 11hLVE. TM ROUT CAM 45l8 IRAA8manTE DESIM IIRASIN NTWW TIE MLIEF As "*am M1P015T8 y
AfD WINIRL SYSTWI trERATINS PMemM.
i j
i
/
j
> ?-
i s
- d ST* LUCIE 2 a.fusang R
op mtsen m j
indu.try Avg. Trend sh'JtDa m E5533 Not Shown U.ing op.CWed. m ops.
ops.
_r
.j i I l I I
I I I
( I I
I l l l l I
I II 1
I I
n
,,I,I,,,I,I,
,,I,,l, w,
l,,,,
,,i, I,,,n,I,
,,I,
,,l,
I j
se,
y
, y l
y 3-3-
y 2-3-
1-1-
1-
,,,, =
n a.m.-= e.-a.
=aar r.a- -
s jis i
3-l b.)
3 o2-1-
1 e
om,
y p
sa ne.ne tw usec sescammm
)1 1.,-
3 e
I-
!g d-j.-. ? t. 7 y-j r, r.
P *..,
yy,b E 5
~
s WM
- n. M b.us oper s.cesar p.,
c g g nas.g.a gsys.,,,
=a j
i l
Il s',*-
J
.,m_
gg,,,,-- 3
~
-# %r4r-Quart.r%49.r,.:
Y e
- ans Amuses, muessen asema e e
B
-}
1 1..
d P.
1 j -
ST. LUCIE 2 t -e s-s.o,*e-r.c GmigrComensman Ergpneertno Wo CPC hM i
SM to 954 Trends and Davistone i
i
{j Deviations From Plant Peer Group
!{
Self-Trond Median
')
Short Term Long Term
,j Desened imp.emed wuse seen
,1 Am Screens While Cenical -
0.54 0.18 l1 l;
Safety Systen 0
0.00
- a j
SignlAcant Evente -
o o
1 6 j
Safety systeen Failures -
0 0.67 i
l Camas Codes @ilISts)
I l*
a Ammmmm e n ome w commemme -
]om oJo l
k ummew commer an== -
o oml l
j s oneom.mmman m.m. -
o c.n
- j a m.m mar o.as om t
+
a romaamme -
o cAo ff tammmmmmmmme -
o 1
IOAE
)
l j S M FT D O W N i
88 duty Systmai NA
-0.16 i >
1 f5 SigalAcant Evente -
NA 0
ii l
Safuty Sysemen Fallures -
NA 1.34 2 !
l Cause Codes h Lefts)
!I'
. Am. m mem mm. -
m m om j
k umannsopm eres== -
m 0Jo C jj
.m-m
)om jj a saammmmmerimaamme -
een
]o.12 a
romaamme -
sea E oR
,j esamm m mmmme -
een 0
6 OUTAegs
+
==
l Forced Outage Itate * -
o 0.49 Egsipannt Forced W * -
0 0.13
!j 1000 Comunercial Cetiteel Hours I
1m o's os o's is
-t m o's o'o o's is i
Performance hdog PerformanceIndes
- .ameosamense.ropemeses cymes
'I I
7e i
o.
1
]
ST. LUCIE 2 li 3
PI EVENTS FOR 94-4 j
BONE I
l PI EVENTS POR 95-1 i
E C E & M 02/21/95 LEnf 30P95002 50.728: 20416 ptst NIST: Po st CPERAflous AT 1005
]
DESC
- A REACTOR TRIP RESULTS PRON A LOW STEAN EERATR LEWL AFTR A STEAR MIERATR LEWL ItsfataENT
'j FAILS NIM, CAUSING THE FEED REWLATIss WLW TO CLOSE.
PI ETENTS POR 95-2 EOMS 1
PI EVENTS POR 95-3 EONE I
t I
a P
i I
i 1
I i
l i
i