ML20215D917
| ML20215D917 | |
| Person / Time | |
|---|---|
| Site: | Perry, Surry, Duane Arnold, Zion, 05000000 |
| Issue date: | 10/06/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| IEIN-86-037, IEIN-86-37, NUDOCS 8610140359 | |
| Download: ML20215D917 (18) | |
Text
._
e OCT 6 1986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON SEPTEMBER 29, 1986 - MEETING 86-34 On September 29, 1986, an Operating Reactor Events meeting (86-34) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on September 22, 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.
Original Signed By:
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.:
See Next Page DISTRIBUTION h tral File b c
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OCT 6 1986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON SEPTEMBER 29, 1986 - MEETING 86-34 On September 29, 1986, an Operating Reactor Events meeting (86-34) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on September 22, 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.
g y
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.:
See Next Page
Harold R. Denton -
cc:
R. Vollmer J. Stefano J. Taylor W. Butler C. Heltemes M. Thadani D. Ross D. Muller T. Murley, Reg. I J. Stewart J. Nelson Grace, Reg. II J. Norris J. Keppler, Reg. III S. Varga R. D. Martin, Reg. IV C. Patel J. B. Martin, Reg. V L. Rubenstein R. Starostecki, Reg. I S. Ebneter, Reg. I R. Walker, Reg. II C. Norelius, Reg. III E. Johnson. Reg. IV D. Kirsch, Reg. V H. Thompson F. Miraglia R. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron B. Boger D. Crutchfield G. Lainas V..Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin P. Baranowsky
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-34)
SEPTEMBER 29, 1986 NAME DIVISION NAME DIVISION G. Holahan NRR/0 RAS W. Swenson NRR/0 RAS M. Virgilio NRR/0 RAS R. Jolliffe IE/DEPER
!!. Garg NRR/ DBL W. Haass IE/QAVT J. Stewart IE/DEPER D. Basdekas RES/DRSS D. Vassallo NRR/ DBL C. Miller NRR/PWRB D. Crutchfield NRR/PWRB G. Cwalina NRR/DHFT B. Boger NRR/DHFT B. Clayton NRR/DPLA R. Frahm NRR/DSR0 W. Regan NRR/PBF0 S. Varga NRR/PWRA V. Benaroya NRR/PAF0 J. Clifford NRR R. Dennig AE00 R. Hernan NRR/PPAS A. Kimmins NOAC/0RNL M. Clausen COM/LZ C. Ader OCM/TR G. Klingler IE/DI/0RPB C. Paperiello RIII/DRS M. Chiramal AE0D/R0AB R. Woodruff IE/DEPER E. Weiss IE/DEPER K. Eccleston NRR/PPAS F. Rosa NRR/PAEl C. Patel NRR/PWDA E. Jordan IE J. Rosenthal IE T. Novak NRR/PWRA E. Rossi NRR/PWRA J. Norris NRR/ PAD 3 R. Houston NRR/ DBL F. Schroeder NRR/PWRB F. Miraglia NRR/PWRB R. Baer IE/DEPER J. Stefano NRR D. Tarnoff NRR/0 RAS
s ENCLOSURE 2 t
OPERATING REACTORS EVENTS BRIEFING 86-3l4 SEPTEMBER 29, 1986
,5 i
(0 PERRY 1 CLASS 1E BUS TRIP SETPOINTS d '
j of DUANE ARNOLD CLASS 1E STATION BATTERY PROBLEM Ic'
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l ZION 2 DEGRADED VOLTAGE - ESF BUS LOSS OF POWER ZION 1 DEGRADATION OF MAIN STEAM LINE CHECK VALVE OTHER EVENT OF INTEREST SURRY 1 MULTIPLE RELAY FAILURE Ill ESF SYSTEM 5
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PERRY 1 - CLASS 1E BUS TRIP SETP0INTS AD SEPTEMBER 18, 1986 - (J. STEFANO, NRR)
(o PROBLEM:
IMPROPER RELAY SETTING FOR CERTAIN DIVISION III BREAKERS RESULTS IN BREAKER COORDINATION PROBLEM CAUSE:
PERSONNEL ERROR SIGNIFICANCE:
FAULT IN SINGLE SAFETY LOAD COULD HAVE CAUSED A LOSS IN THE DIVISION III POWER SUPPLY.
REDUCED MARGIN FOR SELECTIVE TRIPPING ON DIVISION II, ALTHOUGH SELECTIVE TRIPPING IS PRESERVED.
WEAK COMMUNICATION BETWEEN LICENSEE'S ENGINEERING AND OPERATING ORGANIZATION REGARDING PRIORITIES DISCUSSION:
IN RESPONSE TO STAFF REQUEST (8/82), THE LICENSEE COMMITTED IN THE FSAR TO PERFORM BREAKER C0 ORDINATION STUDIES IDI IDENTIFIED NEED FOR ADDITIONAL ACTION ON THIS MATTER (3/26/85)
LICENSEE ENGINEERING STAFF RECOMMENDED SETPOINT CHANGES ~(5/85)
/*
LICENSEE ENGINEERING DEPARTMENT DISCOVERED SETPOINTS HAD NOT BEEN CHANGED (9/18/86).
FOLLOW-UP:
LICENSEE FORMED TASK FORCE TO DETERMINE ROOT CAUSE & PROGRAMMATIC IMPLICATIONS
- RE-REVIEW 8 PRIORITIZATION OF OUTSTANDING SETPOINT CHANGE REQUESTS
- AFFECTED BREAKER SETP0INTS ARE BEING RE-ESTABLISHED REGION III:
FOLLOW-UP INSPECTION TO ASSESS SIGNIFICANCE AND DETERMINE ENFORCEMENT ACTIONS, IF APPROPRIATE
DUANE ARNOLD - CLASS 1E STATION BATTERY PROBLEM O'yt SEPTEMBER 22, 1986 (ERIC WEISS, IE) g PROBLEM:
EXTENSIVE EROSION INSIDE BATTERY NEAR TOP 0F THE PLATES BETWEEN THE PLATES AND SUPPORTS IDENTIFIED BY VENDOR AFTER LICENSEE NOTICED WHITE SEDIMENT IN ELECTROLYTE.
CAUSE:
TEMPERATURE ACCELERATED AGING SIGNIFICANCE:
BATTERIES MEET ALL TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS VENDOR CAN PROVIDE NO CRITERIA TO LICENSEE FOR FUTURE USE IN IDENTIFYING PROBLEM BECAUSE IT RE0 VIRES SKILL AND EXPERIENCE OF QUALIFIED BATTERY TECHNICIAN BATTERY SUPPLIES POWER TO HPCI AND SOME ISOLATION VALVES SEISMIC EVENT COULD DISABLE BATTERY AT TIME WHEN DC POWER IS NEEDED (SANDIA TESTS IDENTIFY THE PLATE TO TERMINAL CONNECTION AS THE SEISMICALLY MOST VULNERABLE PORTION OF STATION BATTERIES)
CIRCUMSTANCES:
PLANT AT 20% POWER LICENSEE PERFORMS VISUAL INSPECTION IN RESPONSE TO INFORMATION NOTICE 86-37 (MAY 16, 1986) WHICH IDENTIFIED EROSION PROBLEM AT RANCHO SECO (MARCH 1986)
LICENSEE NOTICES WHITE SUBSTANCE IN ELECTROLYTE OF 250 VOLT BATTERY AND REQUESTS ASSISTANCE OF BATTERY VENDOR VENDOR REPRESENTATIVE NOTICES THREE PLATES SEPARATED IN ONE CELL AND 50% EROSION OF PLATE TO BUS-BAR CONNECTION IN 11 OTHER CELLS CELLS WERE INSTALLED IN 1971 AND ARE NO LONGER MANUFACTURED 125 VOLT BATTERIES WHICH HANDLE BREAKER MOVEMENT DO NOT EXHIBIT CORROSION VENDOR RECOMMENDS REMOVING ONE CELL FROM SERVICE IMMEDIATELY AND REPLACING OTHER CELLS IN NEAR TERM LICENSEE REQUESTS CONTRACT ASSISTANCE TO TEST 11 CELLS LICENSEE NOTICES 2 OTHER CELLS WITH DEGRADATION
DUANE ARNOLD - CLASS 1E STATION BATTERY PROBLEM SEPTEMBER 22, 1986 (ERIC WEISS, IE)
CIRCUMSTANCES, (CON'T.)
IE CONTACTS VENDOR AND DISCUSSES SEISMIC VULNERABILITY -
1 INFORMATION RELAYED TO LICENSEE VIA RESIDENT INSPECTOR LICENSEE PERFORMS SEISMIC ANALYSIS AND CONCLUDES 14 CELLS MUST BE REMOVED FROM SERVICE - PLANS REPLACEMENT WITH LEAD-CALCIUM VENDOR EXAMINES ROOT CAUSE AND POTENTIAL FOR PART 21 REPORT VENDOR BOARD CONCLUDES PROBLEM CAUSED BY ACCELERATED AGING DUE l
TO DIFFERENTIAL TEMP AND NOT A MANUFACTURING DEFECT VENDOR SAYS PROBLEM IS CONFINED TO PLANTE' DESIGN N0 OTHER PLANTS ARE THOUGHT TO HAVE PLANTE' DESIGN MADE BY THIS VENDOR FOLLOWUP IE EVALUATING GENERIC CONCERNS AND CONSIDERING THE NEED FOR A SUPPLEMENTARY INFORMATION NOTICE OR BULLETIN
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ZION 2 - DEGRADED VOLTAGE - ESF BUS LOSS OF POWER D
SEPTEMBER 21, 1986 - (J. STEWART, IE) f o' n
PROBLEM:
DEGRADED VOLTAGE RELAYS ACTUATED DIESEL START AND ESF BUS LOAD SHED VOLTAGE RECOVERED DURING DIESEL STARTUP AND RESET DEGRADED i
VOLTAGE RELAYS, DIESEL STOPPED, ESF LOADS STILL DISCONNECTED CAUSE:
POTENTIAL DESIGN OVERSIGHT, PERSONNEL ERROR, ELECTRICAL RELAY CHATTER SIGNIFICANCE:
UNIT 2 AT 2% POWER P0TENTIAL LOSS OF ALL ESF BUSES, TEMPORARILY, DUE TO COMMON MODE DEGRADED VOLTAGE SMALL TIME WINDOW (APPR0XIMATELY 10 SEC) THAT LOP COULD INITIATE POSSIBLE INADVERTENT VIOLATION OF IEEE 279, COMPLETION OF SAFETY FUNCTION DISCUSSION:
9/21/86 GRID FLUCTUATIONS RESULT IN DEGRADED VOLTAGE CONDITIONS SENSED AT ESF BUSSES DEGRADED VOLTAGE RELAYS ACTUATE AND INITIATE 5-MINUTE TIMER OPERATORS FAILED TO FOLLOW PROCEDURE BY NOT SHEDDING NON-ESSENTIAL LOADS TIMER TIMED OUT, EDG STARTED, ALL ESF LOADS ON AFFECTED BUS WERE SHED DEGRADED VOLTAGE RELAYS RESET, EDG SHUTS DOWN BEFORE LOCKING ON ESF BUS, ESF LOADS REMAIN DISCONNECTED ZION OPERATORS NOT FULLY AWARE OF DESIGN DIESEL ENGINE START CIRCUITRY KNOWN DEFECTIVE FOLLOWUP:
NRR WILL REVIEW ZION SPECIFICS AND P0TENTIAL DEGRADED VOLTAGE GENERIC ASPECTS, IE WILL ASSIST REGION FOLLOWING PLANT ACTION
ZION 1 - DEGRADATION OF MAIN STEAM LINE CHECK VALVE (MSCV)
SEPTEMBER 24, 1986 - (J. NORRIS, NRR)
PROBLEM:
ALL FOUR MSCVs HAD DAMAGED CONNECTION BETWEEN THE VALVE g
1 DISK AND ROCKER ARM b'I CAUSE:
INSTALLATION ERROR, POOR MAINTENANCE SIGNIFICANCE:
P0TENTIAL FOR FAILURE OF MULTIPLE MSCVs REQUIRED FOR MITIGATION OF MAIN STEAM LINE BREAK ACCIDENT DISCUSSION:
ON MAY 8, 1986 1-B MSCV FAILED WHEN UNIT 1 WAS COMING UP (60% POWER)
- STEAM GENERATOR DELTA P ALARM, HIGH FLUX IN ONE QUADRANT, STEAM FLOW DROPPED, STEAM PRESSURE INCREASED, T UP 1*,
gy T
UP 2* DELTA P ACROSS MSCV 40 LBS (2 - 8 LBS IS NORMAL)
COLD UNIT SHUT DOWN. INSPECTION SHOWED MISSING PARTS AND BROKEN SHAFT ON THE VALVE DISK.
VALVE WAS REPLACED.
IN SEPTEMBER, UNIT 1 STARTED REFUELING OUTAGE.
INSPECTION FOUND MISSING PARTS AND VARIOUS DEGREES OF DEGRADATION ON THREE OTHER MSCVs.
MANUFACTURERS:
SCHUTTE & K0ERTING ZION UNIT 2 CONTINUES OPERATION
- CATASTROPHIC FAILURES ARE DETECTABLE IMMEDIATELY
- MSCVs WILL BE LEAK TESTED AT EACH SHUTDOWN UNTIL NEXT REFUELING
- MSCVs WILL BE INSPECTED AT NEXT REFUELING OUTAGE (SCHEDULED FOR MARCH 1987)
FOLLOW-UP:
l LICENSEE WILL ANALYZE TO DETERMINE ROOT CAUSE REGION III WILL FOLLOW-UP ON CORRECTIVE MEASURES
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OTHER EVENT OF INTEREST SURRY 1 - MULTIPLE RELAY FAILURE IN ESF SYSTEM b
SEPTEMBER 20, 1986 - (C. PATEL, NRR)
@J1 PROBLEM:
NORMALLY ENERGlZED BFD-TYPE RELAYS IN RPS AND ESF SYSTEMS Fall AT SURRY CAUSE:
EQUIPMENT MALFUNCTION SIGNIFICANCE:
FAILURE OF NORMALLY ENERGlZED RELAY COULD CAUSE ESF ACTUATION AND/0R REACTOR TRIP DURING NORMAL OPERATION POTENTIAL GENERIC APPLICABILITY, AT LEAST 16 PLANTS DISCUSSION:
SURRY 1 EXPERIENCED ESF ACTUATION ON 9/16 AT 100% POWER AND ON 9/20 AT HOT SilVTDOWN BOTH EVENTS CAUSED BY FAILED BFD SAFEGUARD RELAY SURRY 2 HAD RELAY FAILURE ON 9/24 AND REPLACEMENT RELAY FAILED 9/27 - 9/28 A NUMBER OF BFD-TYPE RELAY FAILURES IDENTIFIED BY WESTINGHOUSE
- MOST FAILURES DETECTED DURING SURVEILLANCE AND OTHER MAINTENANCE MECHANICAL PROBLEMS AND SOME C0ll PROBLEMS IDENTIFIED
- IE CIRCULAR IN 1976, AND IE BULLETIN 79-25 WESTINGHOUSE MODIFIED DESIGN IN 1981-82 NUMBER OF FAILURES APPEARS INCREASING IN 1984-85 FAILURES APPEAR RELATED TO VOLTAGE INDUCED OVERHEATING, THERMAL AGING, AND CONTROL OF AMBIENT TEMPERATURE LICENSEE T0 IMPLEMENT INTERIM CORRECTIVE ACTION PLAN
- VISUAL INSPECTION IN PERIODIC TEST PERFORMED MONTHLY
- SEPARATION OF RELAYS AND FORCED CIRCULATION WILL BE CONSIDERED BY VEPC0 WESTINGHOUSE TO REDESIGN BFD RELAY IN JANUARY 1987 FOLLOWUP LICENSEE TO SEND FAILED RELAYS TO CONTRACTOR FOR STUDY LICENSEE WILL STUDY OPTIONS TO IMPROVE OVERHEATING CONDITIONS RESIDENT INSPECTOR IS FOLLOWING LICENSEE CORRECTIVE ACTIONS
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P F
i REACTOR SCRAM
SUMMARY
WEEK ENDING 09/28/86 E. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD YTD YTD CATIONS ABOVE DELOW TOTAL 157 15%
I, 09/20/06 PALO VERDE 2
40 A PERSONNEL /MAINT NO 7
2 9
09/24/06 ARI:ANSAS 2
100 A EQUIP / BOP YES 4
3 7
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09/24/96 MCGUIRE 1
100 A UNKNOWN NO 3
0 3
o 09/27/86 ERESDEN 3
66 A EQUIP /CHK VLV NO 2
0 2
SUMMARY
OF COMPLICATIONS g
SITE
' UNIT COMPLICATIONS ARKANSAS 2 PRESSURIZER CODE SAFETY VALVE LIFTED 100 PSI BELOW SETPOINT i
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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 09/28/06 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY l
SCRAMS (5)
AVERAGE AVERAGE j
YTD
( 3) -( 4 )
- TGWER >15%
EQUIP. RELATED
>15%
2 4.8 5.4 (68%)
i FERS. RELATED(6) >15%
1 2.0 2.0 (25%)
{
OTHER(7)
>15%
1 0.6 0.6 ( 7%)
- Subtotal **
4 7.4 G.O
- POWER <15%
EQUIP. RELATED
<15%
0 1.5 1.3 (54%)
PERS. RELATED
<15%
0 0.9 0.9 (08%)
OTHER
<15%
0 0.2 0.2 ( G%)
+
- Subtotal **
t O
2.6 2.4 j
- + Total ***
4 10.0 10.4 1
~~
I MANUAL VS AUTO SCRAMS j
TYFE NUMBER 1986 1985 OF WEEKLY WEEKLY I;
SCRAMG AVERAGE AVERAGE I-YTD i
l j
MANUAL SCRAMS O
1.1 1.0 AUTOMATIC SCRAMS 4
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'b NOTES 1.- - PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS HIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD 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 UNPLANNED REACTOR TRIPS IN 1985. 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 MANUALUNPLANNEDREACTORTRIFSAT93 REACTORS (HOLDINGFULL POWERLICENSES). 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 REACTORS HOLDING A FULL POWER LICENSE.
6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
7.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL l
CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.
9 4
.._____.____,,___,.____,_,___---,._____,,_.,-.___._,,_m.____
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ENCLOSURE 3
~
-h ;e No.
1 10/02/Si 0FERATINS REACTCSS EVENT! MEETING FDLLOWL'? ITEM 5 AS CF PEETINE 86-34 04 SEFTEP.EER 29.1926 (INA!CENLINSMEETINGDATE'K555 VENDOR.FACIL!ffOMER)
MEETIN5 FAClllTY RES80NillLE TASK EESCRIFTION SCHEDULE CLOSED IATE COMP.ENTS COMPLET. E/IOCUMENT.
EnfEE./
ti!55 VENIC8./
. DIVISION /
FEETINS EVENTIESCRIP.
IE!VIDUAL DATE(5)
PEETING. ETC.
- IATE 56-10 Of5TER CREEV NFS. /HOU5TCN W RESCLVE TFE CUE 5ilCN OF THE 10/30/E6 0 FEN
/ /
FOLLOWUP ACTION TO 03/!!/ii EE / LE'JEL
/
ACCEFTA31LITY 0F BLIN3 SWITCHES
/ /
SE INC0RPORATED IN EWITCH SETF thT AND DELETION CF IAILY CHANNEL'
//
FEVIEW 0~ JUNE 1,1986 EVENT AT IRIFT -
CHECK LASSALLE 26-21 VERMCNT YAN)'EE MR /HOLAHAN S.
DETERMINE ETATUS AND 10/ 0/26 0 FEN
/ /
06'I;/E6 EE / FRC3LEMS
/
EFFECTIVENESS C: STA F AND 09/!0/86 WITH ECRA?
LICENEEE ACTION ON
/ /
SDLENDID VALVES PCST-MAINTENANCE TESTINS (BL 23-22).DEVELCF RECOMPENDAT10NS F04 FURTHER AETICN 26-::
MULTI NRR /H005 TON W.
DETERMINE AFFROFRIATE 10/30/36 OPEN
/ /
' 07/07/26 NA /
/
REGULATORY REQUIREMENTS 1ASED 09/30/26 EWCE-FESIDUAL ON FECOMMEG AT10N5 DISCUSSED AT / /
NEAT FEM 3 VAL SRIEFING PUMP / WEAR FING FAILURES -
FOLLOWUF B5-25 SRAND SULF IE / JORDAN E.
ASSESS FDTENTIAL FOR EENERIC 10/30/S6 0 FEN t /
INFCFMATION NOTICE 02/11/E6 GE / CONTROL E00
/
AFPLICABILITY 09/30/96 INFREFAPATION
//
4 WITHDRMAL FROBLEM E5-32 NINE MILE PT 1 NRR /ECSA F.
DISCUS 5 WITH LICENEEE AND 12/24/E6 OcEN
/ /
07/15!Si SE / SCRAF.
NRR /ZWOLINSK! J.
RESICN LICENSEE'S
//
CUTLET VALVE IMPLEMENTATION OF GL G3-23 IN
/ /
DIAPHGRAM REFERENCE TO 09/02/i6 EVENT FAILURE
,