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=Text=
=Text=
{{#Wiki_filter:.   . _ . _ . _ . _ _ _ _ _ _ _ _
{{#Wiki_filter:.
  .                                        A08111986 L
A08111986 L
MEMORANDUM FOR: Harold R. Denton, Director
MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation i
!                          Office of Nuclear Reactor Regulation i
FROM:
FROM:               Gary M. Holahan, Director Operating Reactors Assessment Staff i
Gary M. Holahan, Director Operating Reactors Assessment Staff i


==SUBJECT:==
==SUBJECT:==
==SUMMARY==
==SUMMARY==
OF THE OPERATING REACTORS EVENTS MEETING ON AUGUST 4, 1986 - MEETING 86-27 On August 4,1986, an Operating Reactor Events meeting (86-27) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on July 28, 1986. The list of attendees is included as Enclosure 1.
OF THE OPERATING REACTORS EVENTS MEETING ON AUGUST 4, 1986 - MEETING 86-27 On August 4,1986, an Operating Reactor Events meeting (86-27) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on July 28, 1986. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented
The events discussed and the significant elements of these events are presented in Enclosure 2.
,      in Enclosure 2. In addition, the assignment of followup review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.
In addition, the assignment of followup review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.
Completion dates have been assigned for items in Enclosure 3.     Each assignee should review Enclosure 3 with regard to their respective responsibilities.
Completion dates have been assigned for items in Enclosure 3.
Each assignee should review Enclosure 3 with regard to their respective responsibilities.
Note that several assignments are approaching the due date. Please be responsive and advise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.
Note that several assignments are approaching the due date. Please be responsive and advise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.
Af/
Af/
Line 34: Line 34:


==Enclosures:==
==Enclosures:==
As Stated cc w/ Encl.:
As Stated cc w/ Encl.:
See Next Page
See Next Page
)       DISTRIBUTION .
)
:    'LCentral File     ,4                                                                                               l 1       NRC PDR                                                                                                         .
DISTRIBUTION.
ORAS Rdg                                                                                                         l 1       ORAS Members I
'LCentral File
,4 l
1 NRC PDR ORAS Rdg l
1 ORAS Members I
i
i
\
\\
:          [
pp
pp             D:0 RAS
[]' p/  
[]' p/
,phh g
i                    hBC:0 RAS d
/g'
j/g'
[
                                                                                      ,phh g RNOFF:         RWESSMAN       GHOLAHAN                                               .
hBC:0 RAS D:0 RAS RNOFF:
8 /8 /86         0'48/86           f/II/86                                                                       j i                                                                                                     ,
d RWESSMAN GHOLAHAN i
8608200399 860811                                                                 /'
j 8 /8 /86 0'48/86 f/II/86 j
PDR     ADOCK 05000206 S                     PDR                                                         h [j
i 8608200399 860811
                                                                  -_-_-___________-___-_____--____----__L
/'
h [j PDR ADOCK 05000206 S
PDR L


          ~
~
k, NIG 11586 f 'N -
k, NIG 11586 f 'N -
.    \                                                                                                                                                                                                                             .
\\
Harold R. Denton                                                                                       0
Harold R. Denton 0
          \       cc:                 R. Vollmer                                                                   R. Dudley
\\
            \                         J. Taylor                                                                   G. Lear C. Heltemes                                                                 R. Woodruff i             .                      D. Ross                                                                     D. Lynch
cc:
              '\
R. Vollmer R. Dudley
T. Murley, Reg. I                                                           E. Reeves
\\
.                '1                   J. Nelson Grace, Reg. II                                                     L. Rubenstein
J. Taylor G. Lear C. Heltemes R. Woodruff i
                            \         J. Keppler, Reg. III                                                         D. Hood R. D. Martin, Reg. IV J. Stone 1'J. B. Martin, Reg. V                                                         B. J. Youngblood R                                                                           M. Fairtile h.. Starostecki, Ebneter, Reg.Reg.            I I                                        E. Adensam Rx Walker, Reg. II C.\Norelius, Reg. III                                                                                                                                                                           ,
D. Ross D. Lynch
j                                    E. '0ohnson. Reg. IV                                                                                                                                                                             '
'\\
D. Kirsch, Reg. V I                                   H. Thompson F. Miraglia
T. Murley, Reg. I E. Reeves
.                                    R. Bernero T. Speis       .
'1 J. Nelson Grace, Reg. II L. Rubenstein
W. Russell                                                                                                                                                                                       '
\\
T. Novak
J. Keppler, Reg. III D. Hood R. D. Martin, Reg. IV J. Stone 1'J. B. Martin, Reg. V B. J. Youngblood R
(                                     F. Schroeder W. Houston
M. Fairtile
,                                    B. Sheron D. Ziemann D. Crutchfield G. Lainas V. Benaroya
: h. Starostecki, Reg. I
;                                  W. Regan
. Ebneter, Reg. I E. Adensam Rx Walker, Reg. II C.\\Norelius, Reg. III j
;                                    D. Vassallo
E. '0ohnson. Reg. IV D. Kirsch, Reg. V I
!                                  E. Jordan i                                   E. Rossi R. Baer E. Weiss R. Hernan i                                   S. Showe S. Rubin P. Baranowsky i
H. Thompson F. Miraglia R. Bernero T. Speis W. Russell T. Novak
(
F. Schroeder W. Houston B. Sheron D. Ziemann D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan i
E. Rossi R. Baer E. Weiss R. Hernan i
S. Showe S. Rubin P. Baranowsky i


I AUG 11286 f                                       ENCLOSURE 1 LIST OF ATTENDEE _S.
I AUG 11286 f
OPERATING REACTORS EVENTS BRIEFING (86-27) 4 AUGUST 4, 1986 a
ENCLOSURE 1 LIST OF ATTENDEE _S.
NAME               DIVISION                     NAME         DIVISION G. Holahan         NRR/0 RAS                   W. Swenson   NRR/0 RAS D. Tarnoff         NRR/0 RAS                   S. Black     NRR/PPAS B. Clayton         NRR/DPLA                     D. Persinko   NRR/DHFT W. Regan           NRR/PWR-B                   V. Benaroya   NRR/PAF0 G. Murphy         ORNL/NOAC                   A. Kininins- ORNL/NOAC S. Rubin           AE0D                       .G. Lapinsky   NRR/PWR-A R. Woodruff         IE/EAB                     G. Klingler   IE/DI/0RPB j     J. Stone           IE/DQAVT/VPB               E. Reeves     NRR/ PAD #2 W. Paulson        NRR/PWR-B                    T. Novak      NRR/PWR-A
OPERATING REACTORS EVENTS BRIEFING (86-27)
AUGUST 4, 1986 4
NAME DIVISION NAME DIVISION a
G. Holahan NRR/0 RAS W. Swenson NRR/0 RAS D. Tarnoff NRR/0 RAS S. Black NRR/PPAS B. Clayton NRR/DPLA D. Persinko NRR/DHFT W. Regan NRR/PWR-B V. Benaroya NRR/PAF0 G. Murphy ORNL/NOAC A. Kininins-ORNL/NOAC S. Rubin AE0D
.G. Lapinsky NRR/PWR-A R. Woodruff IE/EAB G. Klingler IE/DI/0RPB j
J. Stone IE/DQAVT/VPB E. Reeves NRR/ PAD #2
]
]
E. Rossi           NRR/PWR-A                   D. Humenanski OCM/LZ
W. Paulson NRR/PWR-B T. Novak NRR/PWR-A E. Rossi NRR/PWR-A D. Humenanski OCM/LZ F. Schroeder NRR/DPLB R. Baer IE/DEPER/EGCB l
  ,  F. Schroeder       NRR/DPLB                     R. Baer       IE/DEPER/EGCB l     T. Colburn       'NRR/ PAD #1                 F. Rowsome   NRR/DHFT S. Varga           NRR/PWR-A                   J. Clifford   NRR/TOSB E. Adensam         NRR/ DBL                     D. Lynch     NRR/ DBL i
T. Colburn
'NRR/ PAD #1 F. Rowsome NRR/DHFT S. Varga NRR/PWR-A J. Clifford NRR/TOSB E. Adensam NRR/ DBL D. Lynch NRR/ DBL i
I I
I I
i i
i
.l l
.l i
4; l
l 4;
l


4 ENCLOSURE 2 i
ENCLOSURE 2 4
            ~
i
OPERATING REACTOR EVENTS BRIEFING 86-27 i                                                       AUGUST 4, 1986 4
~
OPERATING REACTOR EVENTS BRIEFING 86-27 i
AUGUST 4, 1986 4
1 l
1 l
1 SAN ONOFRE 1                                         STEAM PRESSURE TRANSMITTER FAILURE i
1 SAN ONOFRE 1 STEAM PRESSURE TRANSMITTER FAILURE i
4 FARLEY 1                                             DEGRADATION OF ECCS l                                .
4 l
4              FERMI 2                                             INADVERTENT ECCS ACTUATION i
FARLEY 1 DEGRADATION OF ECCS FERMI 2 INADVERTENT ECCS ACTUATION 4
I 0THER EVENTS OF INTEREST i
i I
MCGUIRE 2                                           -FAILED EMERGENCY DIESEL GENERATOR TURBOCHARGER i
0THER EVENTS OF INTEREST i
I GINNA 1                                             RUPTURE OF 6" DRAIN LINE                                         '
MCGUIRE 2
ELB0W IN TURBINE CYCLE f
-FAILED EMERGENCY DIESEL GENERATOR TURBOCHARGER i
I GINNA 1 RUPTURE OF 6" DRAIN LINE ELB0W IN TURBINE CYCLE f
9 i
9 i
l 4
l 4
i s   "
i s


SAN ON0FRE 1 - STEAM PRESSURE TRANSMITTER FAILURE JULY 30, 1986 (R. DVDLEY: NRR)
SAN ON0FRE 1 - STEAM PRESSURE TRANSMITTER FAILURE JULY 30, 1986 (R. DVDLEY: NRR)
PROBLEM:     FAILURE OF PRESSURE TRANSMITTER FOR PRESSURE COMPENSATION OF STEAM FLOW SIGNALS
PROBLEM:
:        SIGNIFICANCE:       SINGLE FAILURE CAUSED FEEDWATER REDUCTION AND DISABLED
FAILURE OF PRESSURE TRANSMITTER FOR PRESSURE COMPENSATION OF STEAM FLOW SIGNALS SIGNIFICANCE:
;                            STEAM FLOW / FEED FLOW MISMATCH RX TRIP i         DISCUSSION:
SINGLE FAILURE CAUSED FEEDWATER REDUCTION AND DISABLED STEAM FLOW / FEED FLOW MISMATCH RX TRIP i
4 7:35 P.M. (7/29) 76% POWER - RAPID DECREASE IN INDICATED STEAM FLOW 4
DISCUSSION:
SIGNAL; CAUSED AUTO-REDUCTION OF FEEDWATER FLOW 5% SG LEVEL CAUSES AFW AUT0-INITIATION MANUAL FW CONTROL RESTORED SG LEVEL
7:35 P.M. (7/29) 76% POWER - RAPID DECREASE IN INDICATED STEAM FLOW 4
,            STEAM FLOW INDICATION RETURNED TO NORMAL j             FEEDWATER CONTROL RETURNED TO AUT0, POWER REDUCED (63%), OPERATOR i             ASSIGNED DURING TRANSIENT, STEAM FLOW THOUGHT TO HAVE EXCEEDED FEED FLOW BY j             25% WITH NO REACTOR TRIP j             1 P.M. (7/30) - STEAM FLOW SPIKED LOW; OPERATOR TOOK MANUAL
SIGNAL; CAUSED AUTO-REDUCTION OF FEEDWATER FLOW 4
)             FEEDWATER CONTROL j             2 A.M. HR LC0 EXPIRED; T.S. REQUIRED RX SHUTDOWN BEGUN j             3:50 A.M. - (31% POWER) AMPLIFIER CARD REPLACED: TRIP FUNCTION RESTORED; POWER INCREASED LATER l       FOLLOW-UP:
5% SG LEVEL CAUSES AFW AUT0-INITIATION MANUAL FW CONTROL RESTORED SG LEVEL STEAM FLOW INDICATION RETURNED TO NORMAL j
!              REGION V SENT TIA TO NRR i             VERIFY ACTUAL STEAM FLOW / FEED FLOW DURING TRANSIENT & RPS RESPONSE l             LICENSEE CONFIRMED THAT LOFW AND FWLB ANALYSES ASSUME l             STEAM FLOW /FEEDWATER FLOW MISMATCH TRIP f             DEDICATED OPERATOR STATIONED AT PANEL l             ANALYSES WERE RERUN WITH OTHER TRIP SIGNALS i
FEEDWATER CONTROL RETURNED TO AUT0, POWER REDUCED (63%), OPERATOR i
l                                     RE-ANALYSIS RESULTS i       FEEDWATER LINE BREAK:
ASSIGNED DURING TRANSIENT, STEAM FLOW THOUGHT TO HAVE EXCEEDED FEED FLOW BY j
l             TRIP ON VARIABLE LOW PRESSURE (14 SEC. vs 5 SEC.)
25% WITH NO REACTOR TRIP j
PRIMARY PRESSURE < 110%                                               i i
1 P.M. (7/30) - STEAM FLOW SPIKED LOW; OPERATOR TOOK MANUAL
LOSS OF FEEDWATER:
)
!              TRIP ON PRESSURIZER HIGH LEVEL
FEEDWATER CONTROL j
* I PRESSURIZER LEVEL TRIP CHANGED (70% --> 50%)
2 A.M. HR LC0 EXPIRED; T.S. REQUIRED RX SHUTDOWN BEGUN j
3:50 A.M. - (31% POWER) AMPLIFIER CARD REPLACED: TRIP FUNCTION RESTORED; POWER INCREASED LATER l
FOLLOW-UP:
REGION V SENT TIA TO NRR i
VERIFY ACTUAL STEAM FLOW / FEED FLOW DURING TRANSIENT & RPS RESPONSE l
LICENSEE CONFIRMED THAT LOFW AND FWLB ANALYSES ASSUME l
STEAM FLOW /FEEDWATER FLOW MISMATCH TRIP f
DEDICATED OPERATOR STATIONED AT PANEL l
ANALYSES WERE RERUN WITH OTHER TRIP SIGNALS i
l RE-ANALYSIS RESULTS i
FEEDWATER LINE BREAK:
l TRIP ON VARIABLE LOW PRESSURE (14 SEC. vs 5 SEC.)
PRIMARY PRESSURE < 110%
i LOSS OF FEEDWATER:
TRIP ON PRESSURIZER HIGH LEVEL PRESSURIZER LEVEL TRIP CHANGED (70% --> 50%)
i
i


                                                                                                            ;                                                .s l                             Loop A                                         [_oo p             g                               goop c                       .i g                    u.                 ea                         %                          ,,4 Flem             ow                         piew             piouy       le d          Floso                           w       M
.s l
.        Stea m he55ure Comp
Loop A
* sob
[_oo p g
()                                         ()                                           O j
goop c
!                                  I                                       ll                                                                                       !
.i u.
i i                                                                                                                                                                     i j                                               FW Flow                                         FW Flow                                                 FW Flow I
ea
I Centroller                                     Coe4rolle r                                             Cedroller I
,,4 g
le d M
Flem ow piew piouy Floso w
Stea m he55ure
()
()
O j
Comp
* sob I
ll i
i i
j FW Flow FW Flow FW Flow I
Centroller Coe4rolle r Cedroller I
I
)
)
1 S. Flow /F. N                                 5 Fleio/F,F7ew                             3. Fleu)/F.Fiao cc p., der i                                                              ca pmter                                     conp.< A m-G-2.5 % )                                     (+ Zs %)                                     (+25%)
1 S. Flow /F. N 5 Fleio/F,F7ew
i                         .
: 3. Fleu)/F.Fiao i
I               i 6/3
cc p., der ca pmter conp.< A m-G-2.5 % )
!                                                                    LJ v
(+ Zs %)
SAN O Nores i                                           g,TRI P             '
(+25%)
RPS I
i 6
I i
/3 LJ v
SAN O Nores i RPS g,TRI P I


l 3
3 I
I                                    FARLEY 1 - DEGRADATION OF ECCS                                                               '
FARLEY 1 - DEGRADATION OF ECCS AUGUST 1, 1986 (R
AUGUST 1, 1986 (R WOODRUFF, IE) i i
WOODRUFF, IE) i i
  !          PROBLEM:       SILT IN SERVICE WATER SYSTEM CAUSED DEGRADATION OF TWO CHARGING PUMPS WHILE THIRD PUMP WAS IN0PERABLE j           SIGNIFICANCE:
PROBLEM:
l                 POTENTIAL LOSS OF ALL CHARGING PUMPS (CP)
SILT IN SERVICE WATER SYSTEM CAUSED DEGRADATION OF TWO CHARGING PUMPS WHILE THIRD PUMP WAS IN0PERABLE j
;.                  ONLY OTHER ECCS PUMPS ARE RHR PUMPS i
SIGNIFICANCE:
CIRCUMSTANCES:                       '
l POTENTIAL LOSS OF ALL CHARGING PUMPS (CP)
  !                  CP "A" WAS'00T OF SERVICE FOR MAINTENANCE AND EXPECTED TO BE IN0PERABLE FOR 2 OR 3 DAYS l                 CP "B" WAS OPERATING AND WAS SECURED WHEN GEARB0X TEMPERATURE j                 EXCEEDED 155'F
ONLY OTHER ECCS PUMPS ARE RHR PUMPS i
  )                 VENDOR SUGGESTS OPERATING WITH CAUTION AB0VE 140*F AND.N0T
CIRCUMSTANCES:
  ;                  OPERATING AB0VE 155'F
CP "A" WAS'00T OF SERVICE FOR MAINTENANCE AND EXPECTED TO BE IN0PERABLE FOR 2 OR 3 DAYS l
  !                  CP "C" WAS OPERATING AT 148'F AND TEMPERATURE WAS INCREASING l                 CAUSE - SILT IN LUBE OIL COOLERS                                                                               ,
CP "B" WAS OPERATING AND WAS SECURED WHEN GEARB0X TEMPERATURE j
j                  CP "C" STABILIZED AT 145'F AFTER ADDITIONAL COOLING WAS PROVIDED j                   CP "B" LUBE OIL COOLERS WERE FLUSHED TWICE AND PUMP WAS RETURNED j                 TO SERVICE l                 CP "C" WAS FLUSHED l
EXCEEDED 155'F
  !          FOLLOWUP:
)
j                 REGION 11 AND IE ARE FOLLOWING-UP j                   INCREASED PREVENTIVE MAINTENANCE FOR SILT REMOVAL FROM SERVICE j                 WATER SYSTEM IS INDICATED                                             ,
VENDOR SUGGESTS OPERATING WITH CAUTION AB0VE 140*F AND.N0T OPERATING AB0VE 155'F CP "C" WAS OPERATING AT 148'F AND TEMPERATURE WAS INCREASING l
i i
CAUSE - SILT IN LUBE OIL COOLERS j
_ _ ,_ _ _ - - -.. _ _ _ __ ___- _ _ ~ ,_ -. _,                  - _.  . _ . . , _ ,
CP "C" STABILIZED AT 145'F AFTER ADDITIONAL COOLING WAS PROVIDED j
CP "B" LUBE OIL COOLERS WERE FLUSHED TWICE AND PUMP WAS RETURNED j
TO SERVICE l
CP "C" WAS FLUSHED l
FOLLOWUP:
j REGION 11 AND IE ARE FOLLOWING-UP j
INCREASED PREVENTIVE MAINTENANCE FOR SILT REMOVAL FROM SERVICE j
WATER SYSTEM IS INDICATED i
i
_ _,_ _ _ - - -.. _ _ _ __ ___- _ _ ~,_ -. _,


FERMI 2 - INADVERTENT ECCS ACTUATION JULY 15, 1986   (NRR/ LYNCH)-
FERMI 2 - INADVERTENT ECCS ACTUATION JULY 15, 1986 (NRR/ LYNCH)-
PROBLEM:   INVALID LOW LEVEL 1, 2, 3 ACTIVATION DURING REACTOR VESSEL HYDRO TEST SIGNIFICANCE:
PROBLEM:
INVALID LOW LEVEL 1, 2, 3 ACTIVATION DURING REACTOR VESSEL HYDRO TEST SIGNIFICANCE:
INVALID ECCS ACTUATIONS DRY START OF DIESELS LACK 0F ATTENTION TO DETAIL DISCUSSION:
INVALID ECCS ACTUATIONS DRY START OF DIESELS LACK 0F ATTENTION TO DETAIL DISCUSSION:
REACTOR VESSEL HYDR 0 IN PROGRESS (150*F, 20 PSI)
REACTOR VESSEL HYDR 0 IN PROGRESS (150*F, 20 PSI)
WATER LEVEL IN REACTOR VESSEL HEAD WITH SMALL BUBBLE "B" RCP OFF     "B" SHUTDOWN COOLING ON OPERATORS SECURED "B" RHR PUMPS CAUSING FLOW REVERSAL IN "B" LOOP AND PRESSURE SPIKE ON REFERENCE LEG PRESSURE SPIKE IN REFERENCE LEG RESULTED IN FALSE LOW LEVEL SIGNALS AND ESF ACTUATIONS INCLUDING:
WATER LEVEL IN REACTOR VESSEL HEAD WITH SMALL BUBBLE "B" RCP OFF "B" SHUTDOWN COOLING ON OPERATORS SECURED "B" RHR PUMPS CAUSING FLOW REVERSAL IN "B" LOOP AND PRESSURE SPIKE ON REFERENCE LEG PRESSURE SPIKE IN REFERENCE LEG RESULTED IN FALSE LOW LEVEL SIGNALS AND ESF ACTUATIONS INCLUDING:
RPS SCRAM DIV. 1 - RHR (LPCI) AUT0 START DIV 1 8 2 - CORE SPRAY DIV, 2 - EDG (DIV     1 EDG IN MAINTENANCE)
RPS SCRAM DIV. 1 - RHR (LPCI) AUT0 START DIV 1 8 2 - CORE SPRAY DIV, 2 - EDG (DIV 1 EDG IN MAINTENANCE)
BUBBLE IN REACTOR VESSEL HEAD ESCAPED THROUGH LEAKING FLANGE PRESSURE PERTURBATION CAUSED BY SYSTEM G0ING SOLID PRESSURE PEAKED AT 380 PSI - THE SHUT 0FF HEAD FOR THE LOW PRESSURE PUMPS FOLLOWUP:
BUBBLE IN REACTOR VESSEL HEAD ESCAPED THROUGH LEAKING FLANGE PRESSURE PERTURBATION CAUSED BY SYSTEM G0ING SOLID PRESSURE PEAKED AT 380 PSI - THE SHUT 0FF HEAD FOR THE LOW PRESSURE PUMPS FOLLOWUP:
PROCEDURES REVISED TO REQUIRE BOTH RCPs AND TO SECURE             l SHUTDOWN COOLING EARLIER                               .
PROCEDURES REVISED TO REQUIRE BOTH RCPs AND TO SECURE SHUTDOWN COOLING EARLIER
l


OTHER EVENTS OF INTEREST MCGUIRE 2 - FAILED EMERGENCY DIESEL GENERATOR TURB0 CHARGER JULY 25, 1986 (J. STONE, IE)
OTHER EVENTS OF INTEREST MCGUIRE 2 - FAILED EMERGENCY DIESEL GENERATOR TURB0 CHARGER JULY 25, 1986 (J. STONE, IE)
PROBLEM   TURB0 CHARGER COMPRESSOR SIDE FAILED CATASTROPHICALLY DURING ROUTINE TESTING SIGNIFICANCE                                                           ,
PROBLEM TURB0 CHARGER COMPRESSOR SIDE FAILED CATASTROPHICALLY DURING ROUTINE TESTING SIGNIFICANCE FAILURE OF TURB0 CHARGERS AFFECTS AVAILABILITY OF EMERGENCY POWER I
FAILURE OF TURB0 CHARGERS AFFECTS AVAILABILITY OF EMERGENCY POWER I           MAY BE GENERIC TO OTHER DIESELS USING BROWN B0 VERI TURB0 CHARGERS CIRCUMSTANCES l
MAY BE GENERIC TO OTHER DIESELS USING BROWN B0 VERI TURB0 CHARGERS CIRCUMSTANCES DIESEL OPERATING AT 4000KW l
DIESEL OPERATING AT 4000KW LOUD NOISE HEARD, LOAD DROPPED TO 1000KW, DIESEL MANUALLY SHUTDOWN COMPRESSOR SIDE BLADES ALL DESTROYED '
LOUD NOISE HEARD, LOAD DROPPED TO 1000KW, DIESEL MANUALLY SHUTDOWN COMPRESSOR SIDE BLADES ALL DESTROYED '
BEARINGS AND SHAFT UNDAMAGED 4
BEARINGS AND SHAFT UNDAMAGED 4
DISCUSSION CAUSE STILL UNDER INVESTIGATION BY LICENSEE APPEARS 3 BLADES BROKE - FATIGUE BROWN B0 VERI ASSISTING NOT AWARE OF ANY SIMILAR FAILURES DIESEL HAD 5000 HOURS ON IT REPLACED TURBOCHARGER BROWN B0 VERI TURB0 CHARGER USED ON OTHER DIESELS FOLLOWUP   NEED FOR FURTHER ACTION WILL BE DECIDED ONCE CAUSE OF FAILURE IS DETERMINED                                                 j i
DISCUSSION CAUSE STILL UNDER INVESTIGATION BY LICENSEE APPEARS 3 BLADES BROKE - FATIGUE BROWN B0 VERI ASSISTING NOT AWARE OF ANY SIMILAR FAILURES DIESEL HAD 5000 HOURS ON IT REPLACED TURBOCHARGER BROWN B0 VERI TURB0 CHARGER USED ON OTHER DIESELS FOLLOWUP NEED FOR FURTHER ACTION WILL BE DECIDED ONCE CAUSE OF FAILURE IS DETERMINED j
i


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GINNA - RUPTURE OF 6" DRAIN LINE ELB0W IN TURBINE CYCLE JULY 29, 1986 - (M. FAIRTILE, NRR)
GINNA - RUPTURE OF 6" DRAIN LINE ELB0W IN TURBINE CYCLE JULY 29, 1986 - (M. FAIRTILE, NRR)
PROBLEM:   WASTAGE FAILURE IN MILD CARBON STEEL ELB0W IN DRAIN LINE BETWEEN 2A MOISTURE SEPARATOR REHEATER AND SA FEEDWATER HEATER SIGNIFICANCE:
PROBLEM:
WASTAGE FAILURE IN MILD CARBON STEEL ELB0W IN DRAIN LINE BETWEEN 2A MOISTURE SEPARATOR REHEATER AND SA FEEDWATER HEATER SIGNIFICANCE:
POTENTIAL PIPE RUPTURES DUE TO EROSION MAY OCCUR NO PERSONNEL INJURY NO DAMAGE TO SAFETY RELATED EQUIPMENT NO RELEASE OF ACTIVITY DISCUSSION:
POTENTIAL PIPE RUPTURES DUE TO EROSION MAY OCCUR NO PERSONNEL INJURY NO DAMAGE TO SAFETY RELATED EQUIPMENT NO RELEASE OF ACTIVITY DISCUSSION:
OPERATORS HEARD SOUND OF RUPTURE AND MANUALLY TRIPPED REACTOR AND TURBINE OPERATORS MANUALLY CLOSED MAIN STEAM ISOLATION VALVES MAIN FEEDWATER CONTINUED TO FLOW TO SGs UNTIL HI-HI SG SIGNAL CAUSED FEEDWATER REGULATOR VALVE TO CLOSE HIGH FLOW IN SGs CAUSED PRIMARY SIDE COOLANT VOLUME SHRILXAGE AND DROP IN PRESSURIZER LEVEL UNTIL FEEDWATER REGULATOR VALVE CLOSED (PREVAILED FOR ABOUT 11 SECONDS)
OPERATORS HEARD SOUND OF RUPTURE AND MANUALLY TRIPPED REACTOR AND TURBINE OPERATORS MANUALLY CLOSED MAIN STEAM ISOLATION VALVES MAIN FEEDWATER CONTINUED TO FLOW TO SGs UNTIL HI-HI SG SIGNAL CAUSED FEEDWATER REGULATOR VALVE TO CLOSE HIGH FLOW IN SGs CAUSED PRIMARY SIDE COOLANT VOLUME SHRILXAGE AND DROP IN PRESSURIZER LEVEL UNTIL FEEDWATER REGULATOR VALVE CLOSED (PREVAILED FOR ABOUT 11 SECONDS)
Line 195: Line 264:


==SUMMARY==
==SUMMARY==
WEEK ENDING 08/03/86 I.
PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD YTD YTD CATIONS ABOVE BELOW TOTAL 15'/.
15%
07/28/86 PRAIRIE ISLAND 2
100 A PERSONNEL NO 3
0 3
07/29/86 GINNA i
100 A EQUIP /LINE BRK NO 1
0 1
07/30/86 HOPE CREEK 1
8A EQUIP /EHC PROB. NO O
7 7
07/30/06 GINNA 1
26 A UNKNOWN NO 2
0 2
08/01/86 FORT CALHOUN 1
86 M EQUIP / ELECT.
NO 2
0 2
08/01/86 COOK 1
25 A UNKNOWN NO 3
0 3
08/02/86 HATCH 1
55 A UNKNOWN NO 3
0 3
08/02/86 COOK 1
12 A UNKNOWN NO 3
1 4
100 A UNKNOWN NO 6
1 7
08/02/86 INDIAN POINT.
2 03/04/86 CATAWBA 2
49 M PERSONNEL / TEST NO 3
2 5
e O
~


WEEK ENDING 08/03/86 I. PLANT SPECIFIC DATA DATE      SITE          UNIT POWER RPS CAUSE              COMPLI-      YTD    YTD        YTD CATIONS    ABOVE BELOW      TOTAL 15'/. 15%
II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 08/03/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5)
07/28/86 PRAIRIE ISLAND      2      100 A  PERSONNEL        NO                3    0          3 07/29/86 GINNA              i      100 A  EQUIP /LINE BRK NO                1    0          1 07/30/86 HOPE CREEK          1        8A  EQUIP /EHC PROB. NO              O      7          7 07/30/06 GINNA              1      26 A  UNKNOWN          NO              2      0          2 08/01/86 FORT CALHOUN        1      86 M  EQUIP / ELECT. NO                2    0          2 08/01/86 COOK                1      25 A  UNKNOWN          NO                3    0          3 08/02/86 HATCH              1      55 A  UNKNOWN          NO              3      0          3 08/02/86 COOK                1      12 A  UNKNOWN          NO              3      1          4 08/02/86 INDIAN POINT.      2  .
AVERAGE AVERAGE YTD (3) (4)
100 A  UNKNOWN          NO                6    1          7 03/04/86 CATAWBA            2      49 M  PERSONNEL / TEST NO                3    2          5 e
** POWER >15%
O
EQUIP. RELATED
                                      ~
>15%
 
2 4.5 5.4 (68%)
II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 08/03/86 SCRAM CAUSE       POWER       NUMBER           1986     -      1985 OF       WEEKLY           WEEKLY SCRAMS (5)       AVERAGE           AVERAGE YTD           (3) (4)
PERS. RELATED(6) >15%
          ** POWER >15%
2 2.1 2.0 (25%)
* EQUIP. RELATED     >15%             2           4.5 PERS. RELATED(6) >15%                                               5.4 (68%)
OTHER(7)
2           2.1               2.0 (25%)
>15%
OTHER(7)           >15%             4           0.4
4 0.4 0.6 ( 7%)
          ** Subtotal **                                                        0.6 ( 7%)
** Subtotal **
8           7.0               8.0
8 7.0 8.0
          ** POWER <15%
** POWER <15%
EQUIP. RELATED   <15%
EQUIP. RELATED
PER.S. RELATED    <15%
<15%
1           1.6               1.3 (54%)
1 1.6 1.3 (54%)
0           1.0               0.9 (38%)
PER.S. RELATED
OTHER             <15%               1           0.2               0.2 ( 8%)
<15%
          ** Subtotal **                                                                   .
0 1.0 0.9 (38%)
2           2.8               2.4
OTHER
          *** Total ***
<15%
10           9.8             10.4 MANUAL VS AUTO SCRAMS                               ~
1 0.2 0.2 ( 8%)
TYPE                           NUMBER           1986             1985 OF         WEEKLY           WEEKLY
** Subtotal **
    '                                    SCRAMS       AVERAGE       AVERAGE YTD MANUAL SCRAMS                       2           0.8               1.0 AUTOMATIC SCRAMS                     8           8.9               9.4 m
2 2.8 2.4
*** Total ***
10 9.8 10.4 MANUAL VS AUTO SCRAMS
~
TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 2
0.8 1.0 AUTOMATIC SCRAMS 8
8.9 9.4 m


NOTES 1.
NOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
                                          ~
~
WITH A PLANT PROCEDURE.
2.
2.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
3.
3.
1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF                     ^
1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF
^
UNPLANNEDREACTORTRIPSIN1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
UNPLANNEDREACTORTRIPSIN1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
: 4. IN 1985, THERE WERE AN. ESTIMATED TOTAL OF 541 AUTOMATIC AND                       -
4.
MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK                             -
IN 1985, THERE WERE AN. ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
FOR ALL REACTORS.                                                                       "
5.
: 5. BASED ON 100 OPERATING REACTORS
BASED ON 100 OPERATING REACTORS 6.
: 6. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
7.
7.
          "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
O
O


            ~
~
ENCLOSURE 3 Page No.     1 08/06/06 OPERATING REACTORS EVENTS MEETING FOLLOWUP ITEMS AS OF MEETINS 86-27 DN AU6UST 4, 1986 (IN ASCENDING MEETING DATE, NSSS VENDOR, FACILITY ORDER)
ENCLOSURE 3 Page No.
MEETING   FACILITY         RESPONSIBLE           TASK DESCRIPTION                 SCHEDULE CLOSED DATE     COMMENTS WUMBERI   N555 VENDOR /   DIVISIDN/                                               COMPLET. BY DOCUMENT, MEETING   EVENT DESCRIP. INDIVIDUAL                                             DATE(S)   MEETING,ETC.
1 08/06/06 OPERATING REACTORS EVENTS MEETING FOLLOWUP ITEMS AS OF MEETINS 86-27 DN AU6UST 4, 1986 (IN ASCENDING MEETING DATE, NSSS VENDOR, FACILITY ORDER)
< DATE 86-10     0) STER CREEK   NRR / HOUSTON W       RESOLVE THE QUEST!DN OF THE       10/30/06 DPEN     / /   FOLLOWUP ACTION TO 03/31/96 6E / LEVEL             /               ACCEPTABILITY OF BLIND SWITCHES   / /                     BE INCORPORATED IN SWITCH SETPOINT                       AND DELETION OF DAILY CHANNEL     / /                     REY!EW 0F JUNE DRIFT                                 CHECK                                                     1,1996$VENTAT LASSALLE B6-21     VERMONT YANKEE   NRR /HOLAHAN 6.       DETERMINE STATUS AND             05/20/06 OPEN     / /
MEETING FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS WUMBERI N555 VENDOR /
06/23/86 6E / PROBLEMS           /               EFFECTIVENESS OF STAFF AND         / /
DIVISIDN/
WliH SCRAM                             LICENSEE ACil0N GN               / /
COMPLET. BY DOCUMENT, MEETING EVENT DESCRIP.
SCtENDID VALVES                       POST-MAINTENANCE TESTINS (SL 03-28).DEVELOPRECOMMENDATIONS FOR FURTHER ACTIDN 86-21     TURKEY POINT     NRR / ROSA F.         CONSIDER REVIEWINS ELECTRICAL   08/30/86 DPEN     / /
INDIVIDUAL DATE(S)
06/23/E6 h / PDTENTIAL           /               SYSTEM 0F PLANT WITH SIMILAR       / /
MEETING,ETC.
FAILURE OF ALL                         SWIN5 BUS DESIGN                 / /
< DATE 86-10
EMERGENCY DIESEL 6ENERATORS B6-23     PEERY           NRR / HOUSTON W.     OBIAIN AND REVIEW INFORMAT10N     08/29/06 OPEN     / /
: 0) STER CREEK NRR / HOUSTON W RESOLVE THE QUEST!DN OF THE 10/30/06 DPEN
07/07/86 6E / FIRE IN           /               RELATED TO RECURRENCE OF FIRE     / /
/ /
OFFSAS CHARC0AL                       AND INVEST 16 ATE PROPOSED       / /
FOLLOWUP ACTION TO 03/31/96 6E / LEVEL
BEDS                                   ACTIONS B6-23     MULTI           NRR / HOUSTON W.     DETERMINE APPROPRIATE           09/30/26 0 FEN     / /
/
07/07/66 NA /                   /               REBULATORY REQUIREMENTS BASED     / /
ACCEPTABILITY OF BLIND SWITCHES
BWRS-RESIDUAL                         ON RECOMMENDATIONS DISCUSSED AT / /
/ /
HEAT REMOVAL                           BRIEFING PUMP / WEAR RINS FAILURES -
BE INCORPORATED IN SWITCH SETPOINT AND DELETION OF DAILY CHANNEL
FDLLOWUP B6-23     MULTI           NRR /EERLINGER C. ASSURE NRR AND IE COORDINATION   08/30/86 DPEN     / /
/ /
07/07/06 NA /                   /               TO DETERMINE THE NEED FOR AN IE   / /
REY!EW 0F JUNE DRIFT CHECK 1,1996$VENTAT LASSALLE B6-21 VERMONT YANKEE NRR /HOLAHAN 6.
PWRS-INADEQUATE                       BULLETIN                         / /
DETERMINE STATUS AND 05/20/06 OPEN
DESIGN OF ECCS                                                                                 '
/ /
PUMP MINIMUM FLOW PATHS
06/23/86 6E / PROBLEMS
, 86-26       PANCHO SECD 1   NRR /RESAN W.         FIND OUT IF PUMPS f,RE USED IN   09/30/96 OPEN     / /
/
, 07/22/E6 SW / EDTH TRAINS         /               DTHER SYSTEMS AT RANCHO SEC0       / /
EFFECTIVENESS OF STAFF AND
OF DECAY HEAT                                                           / /
/ /
REMOVAL DECLARED
WliH SCRAM LICENSEE ACil0N GN
!            TECHNICALLY IN0PERAELE
/ /
SCtENDID VALVES POST-MAINTENANCE TESTINS (SL 03-28).DEVELOPRECOMMENDATIONS FOR FURTHER ACTIDN 86-21 TURKEY POINT NRR / ROSA F.
CONSIDER REVIEWINS ELECTRICAL 08/30/86 DPEN
/ /
06/23/E6 h / PDTENTIAL
/
SYSTEM 0F PLANT WITH SIMILAR
/ /
FAILURE OF ALL SWIN5 BUS DESIGN
/ /
EMERGENCY DIESEL 6ENERATORS B6-23 PEERY NRR / HOUSTON W.
OBIAIN AND REVIEW INFORMAT10N 08/29/06 OPEN
/ /
07/07/86 6E / FIRE IN
/
RELATED TO RECURRENCE OF FIRE
/ /
OFFSAS CHARC0AL AND INVEST 16 ATE PROPOSED
/ /
BEDS ACTIONS B6-23 MULTI NRR / HOUSTON W.
DETERMINE APPROPRIATE 09/30/26 0 FEN
/ /
07/07/66 NA /
/
REBULATORY REQUIREMENTS BASED
/ /
BWRS-RESIDUAL ON RECOMMENDATIONS DISCUSSED AT / /
HEAT REMOVAL BRIEFING PUMP / WEAR RINS FAILURES -
FDLLOWUP B6-23 MULTI NRR /EERLINGER C.
ASSURE NRR AND IE COORDINATION 08/30/86 DPEN
/ /
07/07/06 NA /
/
TO DETERMINE THE NEED FOR AN IE
/ /
PWRS-INADEQUATE BULLETIN
/ /
DESIGN OF ECCS PUMP MINIMUM FLOW PATHS
, 86-26 PANCHO SECD 1 NRR /RESAN W.
FIND OUT IF PUMPS f,RE USED IN 09/30/96 OPEN
/ /
, 07/22/E6 SW / EDTH TRAINS
/
DTHER SYSTEMS AT RANCHO SEC0
/ /
OF DECAY HEAT
/ /
REMOVAL DECLARED TECHNICALLY IN0PERAELE


. Page No.     2 C/08/B6 DPERATIN6 REACTORS EVENTS MEETING FULLDWUP ITEMS AS OF MEETING 86-27 ON AU6UST 4, 1986 IIN ASCENDING MEETING DATE, NSSS VEND 05, FACILITY ORDER)
. Page No.
EETING     FACILITY         RESPONSIBLE           TASK DESCRIPTION                   SCHEDULE CLOSED DATE   COMMENTS NUMBER /   NSSSVEND6R/     DIVISIDN/                                               COMPLET. BY DOCUMENT, EETIN6     EVENT DESCRIP. INDIVIDUAL                                               DATE(S)   MEETING,ETC.
2 C/08/B6 DPERATIN6 REACTORS EVENTS MEETING FULLDWUP ITEMS AS OF MEETING 86-27 ON AU6UST 4, 1986 IIN ASCENDING MEETING DATE, NSSS VEND 05, FACILITY ORDER)
DATE B6-26     RANCHO SECO 1   NRR /REGAN W.         FOLLOWUP DN USE OF FERMINITE IN 08/30/06 DPEN         / /
EETING FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS NUMBER /
07/29/96 BW / BOTH TRAINS       /               PUMPS DRAIN LINE                   / /
NSSSVEND6R/
OF DECAY HEAT                                                             / /
DIVISIDN/
REMOVAL DECLAPED TECHNICALLY INOPERABLE 86-26     RANCHO SECD I   IE / STONE J.         ASSESSTHEPDTENt!ALFOR             08/30/06 CLOSED 08/04/06 07/28/B6 BW / BOTH TRAINS       /               SENERIC APPLICABILITY               / /     ASSESSMENT OF DECAY HEAT                                                             / /       PROVIDED ON REMOVAL DECLARED                                                                   7/31/B6 INOPERABLE File has been deleted.
COMPLET. BY DOCUMENT, EETIN6 EVENT DESCRIP.
INDIVIDUAL DATE(S)
MEETING,ETC.
DATE B6-26 RANCHO SECO 1 NRR /REGAN W.
FOLLOWUP DN USE OF FERMINITE IN 08/30/06 DPEN
/ /
07/29/96 BW / BOTH TRAINS
/
PUMPS DRAIN LINE
/ /
OF DECAY HEAT
/ /
REMOVAL DECLAPED TECHNICALLY INOPERABLE 86-26 RANCHO SECD I IE / STONE J.
ASSESSTHEPDTENt!ALFOR 08/30/06 CLOSED 08/04/06 07/28/B6 BW / BOTH TRAINS
/
SENERIC APPLICABILITY
/ /
ASSESSMENT OF DECAY HEAT
/ /
PROVIDED ON REMOVAL DECLARED 7/31/B6 INOPERABLE File has been deleted.
4
4
                                                -}}
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Latest revision as of 00:33, 7 December 2024

Summary of Operating Reactor Events Meeting 86-27 on 860804 W/Ofc Director,Div Directors & Representatives Re Briefing on Events Which Occurred Since Last Meeting on 860728.List of Attendees & Viewgraphs Encl
ML20206L908
Person / Time
Site: Mcguire, Fermi, Ginna, Farley, San Onofre, 05000000
Issue date: 08/11/1986
From: Holahan G
Office of Nuclear Reactor Regulation
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8608200399
Download: ML20206L908 (16)
v • d • e


Text

.

A08111986 L

MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation i

FROM:

Gary M. Holahan, Director Operating Reactors Assessment Staff i

SUBJECT:

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON AUGUST 4, 1986 - MEETING 86-27 On August 4,1986, an Operating Reactor Events meeting (86-27) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on July 28, 1986. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2.

In addition, the assignment of followup review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3.

Each assignee should review Enclosure 3 with regard to their respective responsibilities.

Note that several assignments are approaching the due date. Please be responsive and advise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.

Af/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

See Next Page

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DISTRIBUTION.

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E. '0ohnson. Reg. IV D. Kirsch, Reg. V I

H. Thompson F. Miraglia R. Bernero T. Speis W. Russell T. Novak

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F. Schroeder W. Houston B. Sheron D. Ziemann D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan i

E. Rossi R. Baer E. Weiss R. Hernan i

S. Showe S. Rubin P. Baranowsky i

I AUG 11286 f

ENCLOSURE 1 LIST OF ATTENDEE _S.

OPERATING REACTORS EVENTS BRIEFING (86-27)

AUGUST 4, 1986 4

NAME DIVISION NAME DIVISION a

G. Holahan NRR/0 RAS W. Swenson NRR/0 RAS D. Tarnoff NRR/0 RAS S. Black NRR/PPAS B. Clayton NRR/DPLA D. Persinko NRR/DHFT W. Regan NRR/PWR-B V. Benaroya NRR/PAF0 G. Murphy ORNL/NOAC A. Kininins-ORNL/NOAC S. Rubin AE0D

.G. Lapinsky NRR/PWR-A R. Woodruff IE/EAB G. Klingler IE/DI/0RPB j

J. Stone IE/DQAVT/VPB E. Reeves NRR/ PAD #2

]

W. Paulson NRR/PWR-B T. Novak NRR/PWR-A E. Rossi NRR/PWR-A D. Humenanski OCM/LZ F. Schroeder NRR/DPLB R. Baer IE/DEPER/EGCB l

T. Colburn

'NRR/ PAD #1 F. Rowsome NRR/DHFT S. Varga NRR/PWR-A J. Clifford NRR/TOSB E. Adensam NRR/ DBL D. Lynch NRR/ DBL i

I I

i

.l i

l 4;

l

ENCLOSURE 2 4

i

~

OPERATING REACTOR EVENTS BRIEFING 86-27 i

AUGUST 4, 1986 4

1 l

1 SAN ONOFRE 1 STEAM PRESSURE TRANSMITTER FAILURE i

4 l

FARLEY 1 DEGRADATION OF ECCS FERMI 2 INADVERTENT ECCS ACTUATION 4

i I

0THER EVENTS OF INTEREST i

MCGUIRE 2

-FAILED EMERGENCY DIESEL GENERATOR TURBOCHARGER i

I GINNA 1 RUPTURE OF 6" DRAIN LINE ELB0W IN TURBINE CYCLE f

9 i

l 4

i s

SAN ON0FRE 1 - STEAM PRESSURE TRANSMITTER FAILURE JULY 30, 1986 (R. DVDLEY: NRR)

PROBLEM:

FAILURE OF PRESSURE TRANSMITTER FOR PRESSURE COMPENSATION OF STEAM FLOW SIGNALS SIGNIFICANCE:

SINGLE FAILURE CAUSED FEEDWATER REDUCTION AND DISABLED STEAM FLOW / FEED FLOW MISMATCH RX TRIP i

DISCUSSION:

7:35 P.M. (7/29) 76% POWER - RAPID DECREASE IN INDICATED STEAM FLOW 4

SIGNAL; CAUSED AUTO-REDUCTION OF FEEDWATER FLOW 4

5% SG LEVEL CAUSES AFW AUT0-INITIATION MANUAL FW CONTROL RESTORED SG LEVEL STEAM FLOW INDICATION RETURNED TO NORMAL j

FEEDWATER CONTROL RETURNED TO AUT0, POWER REDUCED (63%), OPERATOR i

ASSIGNED DURING TRANSIENT, STEAM FLOW THOUGHT TO HAVE EXCEEDED FEED FLOW BY j

25% WITH NO REACTOR TRIP j

1 P.M. (7/30) - STEAM FLOW SPIKED LOW; OPERATOR TOOK MANUAL

)

FEEDWATER CONTROL j

2 A.M. HR LC0 EXPIRED; T.S. REQUIRED RX SHUTDOWN BEGUN j

3:50 A.M. - (31% POWER) AMPLIFIER CARD REPLACED: TRIP FUNCTION RESTORED; POWER INCREASED LATER l

FOLLOW-UP:

REGION V SENT TIA TO NRR i

VERIFY ACTUAL STEAM FLOW / FEED FLOW DURING TRANSIENT & RPS RESPONSE l

LICENSEE CONFIRMED THAT LOFW AND FWLB ANALYSES ASSUME l

STEAM FLOW /FEEDWATER FLOW MISMATCH TRIP f

DEDICATED OPERATOR STATIONED AT PANEL l

ANALYSES WERE RERUN WITH OTHER TRIP SIGNALS i

l RE-ANALYSIS RESULTS i

FEEDWATER LINE BREAK:

l TRIP ON VARIABLE LOW PRESSURE (14 SEC. vs 5 SEC.)

PRIMARY PRESSURE < 110%

i LOSS OF FEEDWATER:

TRIP ON PRESSURIZER HIGH LEVEL PRESSURIZER LEVEL TRIP CHANGED (70% --> 50%)

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FARLEY 1 - DEGRADATION OF ECCS AUGUST 1, 1986 (R

WOODRUFF, IE) i i

PROBLEM:

SILT IN SERVICE WATER SYSTEM CAUSED DEGRADATION OF TWO CHARGING PUMPS WHILE THIRD PUMP WAS IN0PERABLE j

SIGNIFICANCE:

l POTENTIAL LOSS OF ALL CHARGING PUMPS (CP)

ONLY OTHER ECCS PUMPS ARE RHR PUMPS i

CIRCUMSTANCES:

CP "A" WAS'00T OF SERVICE FOR MAINTENANCE AND EXPECTED TO BE IN0PERABLE FOR 2 OR 3 DAYS l

CP "B" WAS OPERATING AND WAS SECURED WHEN GEARB0X TEMPERATURE j

EXCEEDED 155'F

)

VENDOR SUGGESTS OPERATING WITH CAUTION AB0VE 140*F AND.N0T OPERATING AB0VE 155'F CP "C" WAS OPERATING AT 148'F AND TEMPERATURE WAS INCREASING l

CAUSE - SILT IN LUBE OIL COOLERS j

CP "C" STABILIZED AT 145'F AFTER ADDITIONAL COOLING WAS PROVIDED j

CP "B" LUBE OIL COOLERS WERE FLUSHED TWICE AND PUMP WAS RETURNED j

TO SERVICE l

CP "C" WAS FLUSHED l

FOLLOWUP:

j REGION 11 AND IE ARE FOLLOWING-UP j

INCREASED PREVENTIVE MAINTENANCE FOR SILT REMOVAL FROM SERVICE j

WATER SYSTEM IS INDICATED i

i

_ _,_ _ _ - - -.. _ _ _ __ ___- _ _ ~,_ -. _,

FERMI 2 - INADVERTENT ECCS ACTUATION JULY 15, 1986 (NRR/ LYNCH)-

PROBLEM:

INVALID LOW LEVEL 1, 2, 3 ACTIVATION DURING REACTOR VESSEL HYDRO TEST SIGNIFICANCE:

INVALID ECCS ACTUATIONS DRY START OF DIESELS LACK 0F ATTENTION TO DETAIL DISCUSSION:

REACTOR VESSEL HYDR 0 IN PROGRESS (150*F, 20 PSI)

WATER LEVEL IN REACTOR VESSEL HEAD WITH SMALL BUBBLE "B" RCP OFF "B" SHUTDOWN COOLING ON OPERATORS SECURED "B" RHR PUMPS CAUSING FLOW REVERSAL IN "B" LOOP AND PRESSURE SPIKE ON REFERENCE LEG PRESSURE SPIKE IN REFERENCE LEG RESULTED IN FALSE LOW LEVEL SIGNALS AND ESF ACTUATIONS INCLUDING:

RPS SCRAM DIV. 1 - RHR (LPCI) AUT0 START DIV 1 8 2 - CORE SPRAY DIV, 2 - EDG (DIV 1 EDG IN MAINTENANCE)

BUBBLE IN REACTOR VESSEL HEAD ESCAPED THROUGH LEAKING FLANGE PRESSURE PERTURBATION CAUSED BY SYSTEM G0ING SOLID PRESSURE PEAKED AT 380 PSI - THE SHUT 0FF HEAD FOR THE LOW PRESSURE PUMPS FOLLOWUP:

PROCEDURES REVISED TO REQUIRE BOTH RCPs AND TO SECURE SHUTDOWN COOLING EARLIER

OTHER EVENTS OF INTEREST MCGUIRE 2 - FAILED EMERGENCY DIESEL GENERATOR TURB0 CHARGER JULY 25, 1986 (J. STONE, IE)

PROBLEM TURB0 CHARGER COMPRESSOR SIDE FAILED CATASTROPHICALLY DURING ROUTINE TESTING SIGNIFICANCE FAILURE OF TURB0 CHARGERS AFFECTS AVAILABILITY OF EMERGENCY POWER I

MAY BE GENERIC TO OTHER DIESELS USING BROWN B0 VERI TURB0 CHARGERS CIRCUMSTANCES DIESEL OPERATING AT 4000KW l

LOUD NOISE HEARD, LOAD DROPPED TO 1000KW, DIESEL MANUALLY SHUTDOWN COMPRESSOR SIDE BLADES ALL DESTROYED '

BEARINGS AND SHAFT UNDAMAGED 4

DISCUSSION CAUSE STILL UNDER INVESTIGATION BY LICENSEE APPEARS 3 BLADES BROKE - FATIGUE BROWN B0 VERI ASSISTING NOT AWARE OF ANY SIMILAR FAILURES DIESEL HAD 5000 HOURS ON IT REPLACED TURBOCHARGER BROWN B0 VERI TURB0 CHARGER USED ON OTHER DIESELS FOLLOWUP NEED FOR FURTHER ACTION WILL BE DECIDED ONCE CAUSE OF FAILURE IS DETERMINED j

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GINNA - RUPTURE OF 6" DRAIN LINE ELB0W IN TURBINE CYCLE JULY 29, 1986 - (M. FAIRTILE, NRR)

PROBLEM:

WASTAGE FAILURE IN MILD CARBON STEEL ELB0W IN DRAIN LINE BETWEEN 2A MOISTURE SEPARATOR REHEATER AND SA FEEDWATER HEATER SIGNIFICANCE:

POTENTIAL PIPE RUPTURES DUE TO EROSION MAY OCCUR NO PERSONNEL INJURY NO DAMAGE TO SAFETY RELATED EQUIPMENT NO RELEASE OF ACTIVITY DISCUSSION:

OPERATORS HEARD SOUND OF RUPTURE AND MANUALLY TRIPPED REACTOR AND TURBINE OPERATORS MANUALLY CLOSED MAIN STEAM ISOLATION VALVES MAIN FEEDWATER CONTINUED TO FLOW TO SGs UNTIL HI-HI SG SIGNAL CAUSED FEEDWATER REGULATOR VALVE TO CLOSE HIGH FLOW IN SGs CAUSED PRIMARY SIDE COOLANT VOLUME SHRILXAGE AND DROP IN PRESSURIZER LEVEL UNTIL FEEDWATER REGULATOR VALVE CLOSED (PREVAILED FOR ABOUT 11 SECONDS)

NORMAL CONTROLLED C00LDOWN THEN COMMENCED AND PLANT BROUGHT TO H0T SHUTDOWN FOLLOWUP:

RESIDENT INSPECTOR IS ON TOP 0F EVENT; RESIDENT, PROJECT MANAGER, AND F0B HAD CONFERENCE CALL LICENSEE DETERMINED WASTAGE IN MILD STEEL ELB0W CAUSED RUPTURE.

STUDY OF SIMILAR DRAIN SYSTEM ELB0WS AND UT OF SIMILAR ELB0WS UNDERWAY

REACTOR SCRAM

SUMMARY

WEEK ENDING 08/03/86 I.

PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD YTD YTD CATIONS ABOVE BELOW TOTAL 15'/.

15%

07/28/86 PRAIRIE ISLAND 2

100 A PERSONNEL NO 3

0 3

07/29/86 GINNA i

100 A EQUIP /LINE BRK NO 1

0 1

07/30/86 HOPE CREEK 1

8A EQUIP /EHC PROB. NO O

7 7

07/30/06 GINNA 1

26 A UNKNOWN NO 2

0 2

08/01/86 FORT CALHOUN 1

86 M EQUIP / ELECT.

NO 2

0 2

08/01/86 COOK 1

25 A UNKNOWN NO 3

0 3

08/02/86 HATCH 1

55 A UNKNOWN NO 3

0 3

08/02/86 COOK 1

12 A UNKNOWN NO 3

1 4

100 A UNKNOWN NO 6

1 7

08/02/86 INDIAN POINT.

2 03/04/86 CATAWBA 2

49 M PERSONNEL / TEST NO 3

2 5

e O

~

II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 08/03/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5)

AVERAGE AVERAGE YTD (3) (4)

    • POWER >15%

EQUIP. RELATED

>15%

2 4.5 5.4 (68%)

PERS. RELATED(6) >15%

2 2.1 2.0 (25%)

OTHER(7)

>15%

4 0.4 0.6 ( 7%)

    • Subtotal **

8 7.0 8.0

    • POWER <15%

EQUIP. RELATED

<15%

1 1.6 1.3 (54%)

PER.S. RELATED

<15%

0 1.0 0.9 (38%)

OTHER

<15%

1 0.2 0.2 ( 8%)

    • Subtotal **

2 2.8 2.4

      • Total ***

10 9.8 10.4 MANUAL VS AUTO SCRAMS

~

TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 2

0.8 1.0 AUTOMATIC SCRAMS 8

8.9 9.4 m

NOTES 1.

PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.

~

2.

RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.

3.

1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF

^

UNPLANNEDREACTORTRIPSIN1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.

4.

IN 1985, THERE WERE AN. ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

5.

BASED ON 100 OPERATING REACTORS 6.

PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

7.

"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

O

~

ENCLOSURE 3 Page No.

1 08/06/06 OPERATING REACTORS EVENTS MEETING FOLLOWUP ITEMS AS OF MEETINS 86-27 DN AU6UST 4, 1986 (IN ASCENDING MEETING DATE, NSSS VENDOR, FACILITY ORDER)

MEETING FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS WUMBERI N555 VENDOR /

DIVISIDN/

COMPLET. BY DOCUMENT, MEETING EVENT DESCRIP.

INDIVIDUAL DATE(S)

MEETING,ETC.

< DATE 86-10

0) STER CREEK NRR / HOUSTON W RESOLVE THE QUEST!DN OF THE 10/30/06 DPEN

/ /

FOLLOWUP ACTION TO 03/31/96 6E / LEVEL

/

ACCEPTABILITY OF BLIND SWITCHES

/ /

BE INCORPORATED IN SWITCH SETPOINT AND DELETION OF DAILY CHANNEL

/ /

REY!EW 0F JUNE DRIFT CHECK 1,1996$VENTAT LASSALLE B6-21 VERMONT YANKEE NRR /HOLAHAN 6.

DETERMINE STATUS AND 05/20/06 OPEN

/ /

06/23/86 6E / PROBLEMS

/

EFFECTIVENESS OF STAFF AND

/ /

WliH SCRAM LICENSEE ACil0N GN

/ /

SCtENDID VALVES POST-MAINTENANCE TESTINS (SL 03-28).DEVELOPRECOMMENDATIONS FOR FURTHER ACTIDN 86-21 TURKEY POINT NRR / ROSA F.

CONSIDER REVIEWINS ELECTRICAL 08/30/86 DPEN

/ /

06/23/E6 h / PDTENTIAL

/

SYSTEM 0F PLANT WITH SIMILAR

/ /

FAILURE OF ALL SWIN5 BUS DESIGN

/ /

EMERGENCY DIESEL 6ENERATORS B6-23 PEERY NRR / HOUSTON W.

OBIAIN AND REVIEW INFORMAT10N 08/29/06 OPEN

/ /

07/07/86 6E / FIRE IN

/

RELATED TO RECURRENCE OF FIRE

/ /

OFFSAS CHARC0AL AND INVEST 16 ATE PROPOSED

/ /

BEDS ACTIONS B6-23 MULTI NRR / HOUSTON W.

DETERMINE APPROPRIATE 09/30/26 0 FEN

/ /

07/07/66 NA /

/

REBULATORY REQUIREMENTS BASED

/ /

BWRS-RESIDUAL ON RECOMMENDATIONS DISCUSSED AT / /

HEAT REMOVAL BRIEFING PUMP / WEAR RINS FAILURES -

FDLLOWUP B6-23 MULTI NRR /EERLINGER C.

ASSURE NRR AND IE COORDINATION 08/30/86 DPEN

/ /

07/07/06 NA /

/

TO DETERMINE THE NEED FOR AN IE

/ /

PWRS-INADEQUATE BULLETIN

/ /

DESIGN OF ECCS PUMP MINIMUM FLOW PATHS

, 86-26 PANCHO SECD 1 NRR /RESAN W.

FIND OUT IF PUMPS f,RE USED IN 09/30/96 OPEN

/ /

, 07/22/E6 SW / EDTH TRAINS

/

DTHER SYSTEMS AT RANCHO SEC0

/ /

OF DECAY HEAT

/ /

REMOVAL DECLARED TECHNICALLY IN0PERAELE

. Page No.

2 C/08/B6 DPERATIN6 REACTORS EVENTS MEETING FULLDWUP ITEMS AS OF MEETING 86-27 ON AU6UST 4, 1986 IIN ASCENDING MEETING DATE, NSSS VEND 05, FACILITY ORDER)

EETING FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS NUMBER /

NSSSVEND6R/

DIVISIDN/

COMPLET. BY DOCUMENT, EETIN6 EVENT DESCRIP.

INDIVIDUAL DATE(S)

MEETING,ETC.

DATE B6-26 RANCHO SECO 1 NRR /REGAN W.

FOLLOWUP DN USE OF FERMINITE IN 08/30/06 DPEN

/ /

07/29/96 BW / BOTH TRAINS

/

PUMPS DRAIN LINE

/ /

OF DECAY HEAT

/ /

REMOVAL DECLAPED TECHNICALLY INOPERABLE 86-26 RANCHO SECD I IE / STONE J.

ASSESSTHEPDTENt!ALFOR 08/30/06 CLOSED 08/04/06 07/28/B6 BW / BOTH TRAINS

/

SENERIC APPLICABILITY

/ /

ASSESSMENT OF DECAY HEAT

/ /

PROVIDED ON REMOVAL DECLARED 7/31/B6 INOPERABLE File has been deleted.

4

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