ML20155B823
| ML20155B823 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs, Oconee, Wolf Creek, Columbia, 05000000, Trojan |
| Issue date: | 09/20/1988 |
| From: | Jaudon J Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-88-037, OREM-88-37, NUDOCS 8810070091 | |
| Download: ML20155B823 (12) | |
Text
_ _ _ _ _ _ _ _ _
f$8l MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment FROM:
Johns P. Jaudon, Acting Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING SEPTEMBER 20, 1988 - MEETING 88 37 On September 20, 1988, an Operating Reactors Events meeting (88-37) was held to brief senior managers from NRR, OSP, AE00, RES, Conunission Staff, and Regional Offices on events which occurred since our last meeting on September 6, 1988.
The list of attendees is included as Enclosure 1.
Please note that no Operating Reactors Events meeting was held during the week of September 13, 1988.
The events discussed and the significant elements of these events are presented in Enclosure 2. presents a report-to-date of long. term followup assignment: and a summary of reactor scrams.
Two significant events were identi.
fled for input to NRC's performance indicator program. Two events were suggested for long-term followup, i
t Johns P. Jaudon, Acting Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page DISTRIBUTION Centrai /TTe~
<Os I"
jJ ch
,)/ y
,)'
EAB Reading File jh
, j)p (-
Circulating Copy EAB Staff 18 MLReardon, EAB 00udinot EAB
-/,h/})7 i v
.i LKilgore, SECY DFd./.
hl g
POR 8910070091 000920 f)DR ORC NRRD
~
)FC :EA DEA
- AC yB/00EI iAME :ML at o
- i a ; don
.....:............:.).......:............:............:............:............:...........
) ATE :09/)O/88
- 09/
/88 OFFICIAL RECORD COPY
6 I
CC:
T. Murley, 12G-18 H. Pastis, 14H-25 F. Miraglia, 12G-18
- 0. Matthews, 14H 25 J. Sniezek, 12G-18 R. Samworth, 13E-16 E. Jordan, AE00 G. Knighton, 13E-16 J. Taylor, I?G-13 S. McNeil, 14B-2 i
E. Beckjord, NL-007 R. Capra, 148-2 W. Russell, R1 P. O'Connor, 130-18 J. N. Grace, Ril J. Calvo, 130-18 I
B. Davis, Rill T. Chan, 13E-16 R. D. Martin, RIV J. B. Martin, RV W. Kane, R1 L. Reyes, Ril E. Greenman, R!l!
L. Callan, Rly D. Kirsch, RV S. Varga, 14E-4 F
G. Lainas, 14H 3 i
G. Holahan, 13H-4 L. Shao, 8E-2 J. Partlow, 70-24 7
B, Grimes, 9A 2 F. Congel, 10E-4 i
E. Weiss, AE00 L
T. Martin, E00 J. Guttmann, SECY A. Thadani, 7E 4 S. Rubin, AE00 J. Forsyth, INPO R. Barrett, 10E-2 H. Harper, MNBB 4210 W. Lanning, MNBB 3302 u
B
/
UNITED STATES E'
'o'%
NUCLEAR REGULATORY COMMISSION
,(
WASHING TON, D. C. 20665 3, *-
sd f
SEP 2 0 se6 MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment FROM:
Johns P. Jaudon, Acting Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING September 20, 1988-MEETING 88-37 I
On September 20, 1988, an Operating Reactors Events meeting (88-37) was held ta brief senior managers from NRR, OSP, AE00 RES, Commission Staff, and Regional Offices on events which occurred since our last meeting on September 6, 1988.
The list of attendees is included as Enclosure 1.
Please note that no Operating Reactors Events meeting was held during the week of September 13, 1988.
The events discussed and the significant elements of these events are presented in Enclosure 2. presents a report-to-date of long-term followup assignments and a summary of reactor scrams. Two significant events were identi-fied for input to NRC's performance indicator program.
Two vents w re suggested for long-term followup.
d Johns P. Jaud
. Actin hief Events As es ent Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
f See Next Page L
[
ENCLOSURE 2 4
1 OPERATING REACTORS EVENTS BRIEFING 88-37 I
EyENTS ASSESSMENT BRANCH LOCATION:
12-B-1] WHITE FLINT l
TUESDAY, SEPTEMBER 20, 1988, 11:00 A.M.
i I
L
[
4 0CONEE UNIT 3 LOSS OF RHR COOLING OURING EMERGENCY, POWER SWITCHING LOGIC TESTING 1
WNP UNIT 2 LIQUID NITROGEN RUPTURES PURGE SYSTEM l
l CALVERT CLIFFS UNIT 1 FATAllTIES AND WOLF CREEK I
TROJAN PROBLEMS WITH SW AND PERSONNEL ERRORS i
i i
1 l
2 1
i I
l I
i l
l
88-37 OCONEE UNIT 3 LOSS OF RHR COOLING DURING EMERGENCY POWER SWITCHING LOGIC TESTING SEPTENBER 11, 1988 i
PROBLEM DURING TESTING OF THE EVERGENCY POWER SWITCHING LOGIC, POWER WAf LOST TO THE 4,16KV MAIN FEEDER BUSES FOR APPR0XIMATELY 15 MINUTES, CAUSING A LOSS OF RHR COOLING UNTil POWER WAS RESTORED, THE PLANT WAS IN A REFUEllNG OUTAGE WITH THE VESSEL DRAINED DOWN TO MID-LOOP, CAUSE PERSONNEL ERRORS (P00F COMMUNICATION BETWEEN THE INDIVIDUALS SUPERVISING AND PERFORMING THE TEST) AND POOR TEST PROCEDURES,
. SIGNIFICANCE LOSS OF RHR SHUTDOWN C00LIN2 DURING MID-LOOP OPERATION COULD POTENTIALLY 0
0 RESULT IN FUEL DAMAGE, FOR THIS EVENT, RCS HEATUP WAS 11 F (FROM 95 0
T0 106 F); CAPABILITY EXISTED TO PROVIDE ADDITIONAL VESSEL INVENT 0PY IF NEEDED (INCLUDING GRAVITY FEED FROM BWST),
DISCU$$10N o
ON SEPTEMBER 11, 1988 PRIOR TO BEGINNING THE EMERGENCY POWER SWITCHING LOGIC TEST THE TEST WAS DISCUSSED BY THE SRO, A TEST ENGINEER, AND AN E00lPMENT OPERATOR, o
THE TEST FOR MAIN FEEDER BUS (MFB) N0, 2 (GEE ATTACHED DIAGRAM) WAS I
SUCCESSFULLY COMPLETED AND THE LICENSEE WAS PREPARING TO PERFORM THE TEST FOR MFB NO, 1, o
MFB N0, 1 AND MFB N0, 2 WERE BOTH BEING FED VIA BREAKER El FROM THE UNlT STARTUP TRANSFORMER (THE BUSES WERE INTERCONNECTED THROUGH THE 4,16KV SWITCHGEAR),
o AN EQUIPMENT OPERATOR REMOVED THE CONTROL POWER FUSES FOR BREAKER El PER THE TEST PROCEDURE TO PREVENT IT FROM INADVERTENTLY OPENING i
DURING THE TEST.
NEITHER THE FUSES NOR THE BREAKER WERE TAGGED, CONTACT:
R. KENDALL
REFERENCE:
50,72 # 13426 i
i
0,CONEE. UNIT 3 88-37 o
SEVERAL HOURS LATER THE EQUIPMENT OPERATOR, WHO MAY HAVE BEEN CONFUSED FROM USING A GENERIC BREAKER REMOVAL AND RESTORATION (R8R) PROCEDURE IN ADDITION TO THE TEST PROCEDURE, CALLED THE CONTROL ROOM TO GET PERMISSirN TO REINSTALL THE FUSES, o
THE UNIT SUPERVISOR GAVE PERMISSIONj THE SRO AND TEST ENGINEER WERE NOT CONSULTED, i
o BREAKER El TRIPPED OPEN UPON REINSTALLATION OF THE FUSES (RESULTING IN LOSS OF POWER TO BOTH MAIN FEEDER BUSES AND RHR PUMP "A") BECAUSE A VARIAC USED TO SIMULATE LOW VOLTAGE ON THE UNIT STARTUP TRANSFORMER WAS STILL CONNECTED, BREAKER El COULD NOT BE RECLOSEO, o
STANDBY BREAKERS ($1 AND S2) WERE MANUALLY CLOSED TO RESTORE POWER TO MFB N0s, 1 & 2 AND RHR PUMP "A",
CORRECTIVE ACTIONS THE TEST PROCEDURE HAS BEEN REVISED T0:
1 REQUIRE TAGGING OF THE FUSES AND BREAKER HANDLE, 2, PROVIDE ADDITIONAL GUIDANCE FOR RESTORATION OF POWER IF LOST,
- 3. REQUIRE A VESSEL LEVEL 0F 65 INCHES PRIOR TO CONDUCTING THE TEST THE VESSEL LEVEL DURING THE EVENT WAS 11 INCHES (AB0VE CENTERLINE OF HOT LEG WHICH IS SEVERAL FEET ABOVE TOP OF CORE),
NOTE:
LOSS OF RHR COOLING DURINb MID-LOOP OPERATION WAS ADDRESSED IN INFORMATION NOTICE 86-101 AND GENE 9tC LETTER 87-12.
FOLLOWUP o
REGION 11 IS MONITORING LICENSEE ACTIONS, 0
NRC IS PREPARING TO ISSUE A GENERIC LETTER CONCERNING DECAY HEAT REMOVAL PROBLEMS AT PWR PLANTS DURING MID-LOOP OPERATION (APPROVED BY CRGR; SCHEDULED FOR RELEASE IN OCTOBER 1988),
+
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (88-37)
September 20, 1988 r
NAME ORGANIZATION NAME ORGANIZATION i
UT Crutchfield NRR/DR5P FT Baranowsky NRR/00EA S. Varga NRR/0RP B. Boger NRR/ADR-1 G. Lainas NRR/ADR-2 J. Jaudon NRR/00EA C. Schulten NRR/00EA H. L. Reardon NRR/00EA C. E. Rossi NRR/00EA T. Silko AE00 W. Minners RES/DRPS R. Auluck OSP/TVA G. M. Holahan NRR/0RSP T. Combs CA/GPA i
P. L. Eng Rill ORP S. Scholl NRR/00EA A. Vietti-Cook OCM/LZ R. Samworth NRR/PD-5 S. McNeil NRR/P01 1 P. O'Connor NRR/PD-4 R. Capra NRR/P01-1 S. Juergens SECY T. Staker RIV T. Chan NRR/PD-5 M. Johnson OE00
- 0. Matthews NRR/P02-3 H. Pastis NRR/P02-3 E. Greenman R!l!
I C. Haughney NRR/OR15 J. Zwolinski NRR/0LPQ T. M. Novak AE00/OSP N. Wagner NRR/ DEST j
I l
Occurr Unir 3
'Pown Dismsu7 ION ra 4./6 kV Mais ferDa 'Susa n
/35 AV
/00kV N
po gy g3 NW (Ang
/ ROM $WirdNYAK'D UNDGRfatouND W 0fg (LEC STEAM)
%N OWW (oosr.owgf) ggoM gr mr,,-
r,.~
rrrrn
- u. 3
)
UNlr UNIT
__.AultUAKY
$7nt7pp NAN $R'tMhR fyygyggggs Ha. 37 He. C73 y
N ryryn errW rrrvn fyr Yn dw w m E sm oot frfW (YY% NO dTS U ury 3 TRA M W wiu wsu%
No. cT4 g% '57ANV6Y
<^
$0umES
)
)
m 4
souser (s) 6 9 AV
)
Swag AprM44 Souet x
, n a z
(<v)
)
)N1
)SA
)ff
)Ez
)N1
) S2.
4.IbhV Sus No 1 (canan) pgpg
~ Bus AG.t.
Heews)
~
frrwt Susts w
u l
s s
r_
4.14 kV 4 likV 4,jfky roz) ras.) )rtz n2 )
)rcr.ro; )
5 **
sws*
swas STE STD
( 37C
_ c.eAv)
(vru.ow)
(stus) _
H PZ "d "
eHtZ"S'
- H PE "h*
e e 4.Fr 'A' Utd4 "A*)
. g.py '3 (1 taw, Y)
. g,py c' ( gy n 'd"
.Rp SLDG 3 FRAY 'A'
,'R, M SPEAY3' n
88-37 WASHINGTON NUCLEAR PC' DER UNIT 2 ll0VID NITROGEN RUPTURES PURGE SYSTEM SEPTEMBER 9, 1988 PROBLEM CONTAINMENT PURGE SYSTEM LINE RUPTURED AT rhE WELD WHERE IT CONNECTS TO THE NITROGEN SYPPLY LINE.
CAUSE INADEQUATE CONTROL OVER THE CONDUCT OF CONTAINMENT INERTING AND NITROGEN SUPPLY TANK REFILLING OPERATIONS RESULTED IN LIQUID NITROGEN PASSING THROUGH CONTAINMENT PURGE SYSTEM PlPING.
(
i SAFETY SIGNIFICANCE ANOTHER CASE OF INADEQUATE PLANT PROCEDURES AND INATTENTION TO THE CONDUCT OF OPERATIONS BY MANAGEMENT IN LIGHT OF GENERIC COMMUNICATIONS, (SURRY REFUEllNG CAVITY FLOOR SEAL; OR BRIEFING 88-36)
DISCUSSION 1715 HRS. - ON SEPTEMBER 9, 1988 THE PLANT WAS IN STARTUP WITH CONTAINMENT INERTED TO THE IS REQUIRED LIMIT OF 3.5% 0XYGEN.
1735 HRS. - WHEN A TANK TRUCK ARRIVE 0 TO REFILL THE NITROGEN SUPPLY TANK THE E0 WAS INSTRUCTED BY A SHIFT SUPPORT SUPERVISOR (SRO)
TO PROCEED WITH CONTAINMENT INERTING.
1835 HRS. - 3 AUTOMATIC VALVES WERE IN MANUAL OPERATION DUE 10 i
EQUIPMENT PROBLEMS.
STEAM PRESSURE CONTROL VALVE WHICH PROVIDES HEAT TO SKID FOR VAPORIZING NITROGEN.
TEMPERATURE CONTROL VALVE ON THE SKID WHICH REGULATES NITROGEN OUTLET TEMPERATURE.
PRESSURE CONTROL VALVE WHICH REGULATES THE NITROGEN OUTLET PRESSURE TO 30 PSIG.
i o
MANUAL OPERATION OF THE INERTING SYSTEM IS NOT PROHlBITED.
SIMULTANE0US OPERATION OF FILLING SUPPLY TANK AND INERTING NOT PROHIBITED.
1900 HRS. (APPR0X) - FLASK PRESSURE DROPS FROM 190 PSIG TO 170 PSIG.
CONTACT:
C. SCHULTEN
REFERENCE:
MORNING REPORT 09/12/88
WNP UNIT 2 88-37 o
EO WALKS 20 FT TO TANKER TO GET PRESSURE B00STED, l
1905 HRS, - WHEN E0 RETURNS TO SKID P/T ARE WITHIN THEIR RANGE, E0 IS NOT AWARE THAT GAUGE HAS TRAVELED 360 DEGREES BECAUSE GAUGE STOPS ARE MISSING, 1910 HRS, - CONTROL ROOM INFORMEP BY E0 THAT HIS FLOW NOISE WAS LOST, 1916 HRS, - FIRE WATCH HEARS LOUD BANG ON 501 LEVEL, 1917 HRS, - E0 ISOLATES SUPPLY TANK, 1918 HRS, - TWO CRACKS FOUND ON THE HEAT EFFECTED ZONE OF THE 30-INCH PURGE LINE WHERE IT JOINS TO THE 6-INCH SUPPLY LINE, LIQUID NITROGEN FROSTED SUPPLY LINE, FROST FOUND 8-INCHES INSIDE OF OUTB0ARD CONTAINMENT ISOLATION VALVE, f
CORRECTIVE ACTION o
50 GALLONS OF LIQUID NITROGEN WAS NOT ACCOUNTED FOR, o
(LRT PERFORMED ON CIVs INDICATES WITHIN 1% OF TS LIMIT, o
VENDOR CONTACTED RE:
CRYOGENIC EXPOSURE OF CIVs.
o CONTAINMENT DEINERTED TO ALLOW MAGNETIC PARTICLE INSPECTION OF PURGE I
SYSTEM WELDS LOCATED INSIDE DRYWEl.L PENETRAT10N, o
LLRT PERFORMED 2ND TIME ON CIVs.
FOLLOWUP o
GENERIC COMMUNICATIONS ON THIS SUBJECT ISSUED IN 1984/1985 IE BULLETIN 84-01 (02/03/84)
GE Sil 402 (02/14/84)
IE INFORMATION NOTICE 84-17 (03/05/84) il 2500/12 (02/07/85) o REGION V IS FOLLOWING LICENSEE CORRECTIVE ACTIONS,
4
,ASHINGTON NUCLEAR POWER UNIT 2 W
CONTAINMENT NITROGEN INERTING
'~r
" "" '.J
'*U r'
- ===
i i
i Ii I,
1'
. 1
{ 'a i;
,,s...<
9; g
l,i i*
g v.s i i...
1 i
I I
._ _ __ A l ()
Il r---~~ll-lli
}ww,,,
l g 'U,J d f~,,,>
f""....
lI i'
'a t
i i
8' w, i8I 19I:
n..
i 8
i i
- [.
t g
i '"...
q.n m;
I j
_J j li ll
"p l a,';',* " a
. ~0; iI I
8 1o J
li p m....
Ii l
i it n+
- g I !...'".t" '!'.li u l1 I
ii
~~G Di ig ll tr E
ll i.n.
sh.
lg g
BMW4 L lI 1
.J '.i',
ll cepep4acA Dii
- ue iI I.
,! r- - -
- - - - - - -- ~ Y h,
b ll e.
1,.
i it 7
I ll[
l1 l
W
- l lI I
Iwv4 g1 lI ll,','J'j"
.... A I
(~~
,a
- I I
l
-< e.. \\: (.i n..
[g i l,,,,
I
- g
,(,.'..
I n4 I
Iig N
.i=*i 9, II:
r
. :. = ::,,,
ll
- 1 l
g y,
y' < >-
l o
,, e ii, ll 131 1
1 J h,:
e
'I f j ;
's I I 11 i l II Il jl q, w-p' ' g e eii m
c &
.y.-
.u u_
ig n
fa.'t,'.
ll
. e':
l I,I 8 Y..
1.$"fB':i'E'{'1.'Et **"i_My._._._.
ii t
t ii D
1i n
i lI
. 6.. i.. m _ *f P
!I
~' ~..%
7 '
.i.fi og.c4 - $ER,0.
II
/.e....
ll u.....
l-
- * =.....
lgn w n g.
-n 7.
31 er _ a mic.s.
n L _"-i!!,'.".O'7".'I h " --
- = -- r, i l
F 1
e e e O
p AM N
--N-g, gv t
/
N--,J,/y g,
y'f N
gp'Hq
.wb 9b+
VA<., Sagang VAC
--t SKr.5W->
WASHINGTON NUCLEAR POWER UNIT 2 CONTAINMENT NITROGEN INERID 3 i
P
.