ML20215G136

Summary of 861006 Operating Reactor Events Meeting 86-35 Re Events Since Last Meeting on 860929.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Attendance List & Viewgraphs Encl

ML20215G136
Person / Time
Site:	Oconee, Palisades, Point Beach, Oyster Creek, Hope Creek, Columbia, 05000000
Issue date:	10/14/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8610200104
Download: ML20215G136 (23)

Text

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W 14 R

-MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff ,

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON OCTOBER 6, 1986 - MEETING'86-35 On October 6,1986, an Operating Reactor Events meeting (86-35) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on September 29, 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.

M/. i Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

See Next Page DISTRIBUTION w 1 Central /F11e-NRC PDR ORAS Rdg ORAS Members h

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Out 14 WE6 Harold R. Denton cc: R. Vollmer H. Pastis J. Taylor H. Bailey C. Heltemes J. Stolz D. Ross T. Wambach T. Murley, Reg. I A. Thadani J. Nelson Grace, Reg. II J. Bradfute J. Keppler, Reg. III E. Adensam R. D. Martin, Reg. IV V. Hodge 1 J. B. Martin, Reg. V T. Colburn R. Starostecki, Reg. I G. Lear S. Ebneter, Reg. I J. Donohew R. Walker, Reg. II R. Becker C. Norelius, Reg. III J. Zwolinski E. Johnson. Reg. IV D. Wagner D. Kirsch, Reg. V C. Shulten 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

15. Rubin P. Baranowsky

00F14 W ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-35)

OCTOBER 6, 1986 NAME DIVISION NAME DIVISION M. Caruso ORAS/NRR D. Jolliffe IE/DEPER K. Jabbour PWR-A/NRR M. Chiramal AE0D R. Ramirez DBL /EICSB D. Basdekas DRSS/RES S. Rhow EICSB/NRR G. Cwalina DHFT/NRR C. Miller PWR-B/NRR M. Clausen OCM/LZ R. Dudley DPLA/NRR T. Wambach DPLB/NRR R. Hernan PPAS/NRR C. McCracken PDBf6/NRR D. Vassallo F0B/ DBL C. Shulten F0B/ DBL R. Scholl ORAS/NRR W. Paulson PWR-B/NRR W. Regan PWR-B/NRR V. Hodge EGCB/IE A. Kimmins ORNL/NOAC ..

.V. Benaroya PAF0/NRR J. Bradfute DBL /NRR A. Dromerick IE/DEPER/EGCB G. Klingler ORPW/IE J. Stone IE/DQAVT/VPB R. Becker DBL /NRR E. Weiss IE/DEPER/EAB E. Jordan IE R. Starostecki IE A. Thadani NRR J. Rosenthal IE/EAB C. Rossi PWR-A/NRR J. Stolz PWR-B/NRR H. Pastis PWR-B/NRR F. Schroeder PWR-B/NRR R. Houston DBL /NRR T. Colburn PWR-A/NRR R. Baer IE/DEPER G. Holahan ORAS/NRR

.___m.,

ENCLOSURE 2' OPERATING REACTORS EVENTS BRIEFING 86-35 0CTOBER 6, 1986 0CONEE 2 LOSS OF LOW PRESSURE SERVICE WATER (LPSW)

PALISADES SERVICE WATER PUMPS DO NOT MEET FSAR REQUIREMENTS ~

WNP2 NO ANALYSIS OF POTENTIAL FLOODING DUE TO FIRE POINT BEACH 2 BOTH MSIVs FAIL TO CLOSE FULLY ON MANUAL DEMAND OTHER EVENTS OF INTEREST OYSTER CREEK CONTROL R0D DRIVE HYDRAULIC CONTROL UNITS NOT INSTALLED AS DESIGNED HOPE CREEK LOSS OF 0FFSITE POWER TEST - UPDATE l

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OCONEE 2 - LOSS OF LOW PRESSURE SERVICE WATER (LPSW)

OCTOBER 1, 1986 - (H. BAILEY, IE)

PROBLEM: LPSW COOLING FAILED ON UNIT 2

. SIGNIFICANCE: LOSS OF ULTIMATE HEAT SINK. DESIGN DEFICIENCY MAY BE APPLICABLE TO OTHER PLANTS CIRCUMSTANCES:

LPSW PUMPS ON UNIT 2 LOST SUCTION AFTER ABOUT 1 HOUR OF OPERATION FOLLOWING LOAD SHED TEST WITH CONDENSER CIRCULATING (CCW) WATER PUMPS IDLED.

SUCTION REGAINED AFTER CROSS CONNECT TO UNIT 1 WAS OPENED.

CCW GRAVITY FLOW TEST ON UNIT 2 FAILED. LPSW SUCTION FROM UNIT 1.

CCW USES SIPHON FOR FLOW OVER HIGH POINT, ULTIMATE HEAT SINK ON UNITS 1 AND 2 DECLARED INOPERABLE PER T/S. UNITS SUBSEQUENTLY TAKEN TO COLD SHUTDOWN.

FLANGE LEAKS ON UNIT 2 CCW PUMPS SEALED. PASSED CCW GRAVITY FLOW TEST.

KE0 WEE LAKE LEVEL FOR TEST A CONCERN. CURRENT LEVEL 785 FT.

NORMAL LAKE LEVEL 800 FT. MINIMUM TECH SPEC LEVEL 0F 775 FT.

FOR KE0 WEE HYDRO EMERGENCY POWER. CCW PUMP HAS A FLANGE AT HIGH POINT IN SYSTEM.

FOLLOWUP:

REGION II HAS LEAD FOR RESTART LICENSEE TO DEMONSTRATE OPERABILITY OF LPSW SYSTEM PRIOR TO RESTART

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PALISADES - SERVICE WATER PUMPS DO NOT MEET FSAR FLOW REQUIREMENTS SEPTEMBER 30, 1986 - (H. BAILEY,-IE)

PROBLEM: THREE SERVICE WATER PUMPS DO NOT MEET THE FSAR FLOW REQUIREMENTS SIGNIFICANCE: ULTIMATE HEAT SINK MAY NOT BE ADEQUATE TO MITIGATE THE DESIGN BASIS LOCA CIRCUMSTANCES:

SEVERAL SYSTEMS HAVE BEEN FLOW TESTED DURING THE CURRENT OUTAGE AND DISCREPANCIES HAVE BEEN FOUND. THE LATEST IS THE SW SYSTEM THREE SERVICE WATER PUMPS ARE APPR0XIMATELY 10% LOW ON FSAR FLOW (8000 GPM AT 140 FEET)

IT IS NOT KNOWN AT THIS TIME IF THE LOW FLOW IS CAUSED BY DEGRADATION OR HAS ALWAYS BEEN THIS WAY. ALSO NOT KNOWN IF FSAR FLOW-IS ACTUALLY REQUIRED PLANT TECH SPECS SPECIFY 10 CFR 50, SECTION 50.55E(G) WHICH REFERS TO ASME CODE, SECTION XI. PREVIOUS FLOW TESTING HAS BEEN FOUND TO BE INADEQUATE TO DETECT SYSTEM FLOW DEGRADATION, PUMP SURVEILLANCE PER ASME SECTION XI USUALLY LOOKS AT PARAMETERS WHILE ON MINIFLOW.

IN ADDITION, VARIANCES IN FLOW ALLOWED BY SECTION XI 0FTEN OUTSIDE THE FSAR VARIANCES.

REGION III HAS INV0KED L0 CFR 50, APPENDIX B, CRITERION XI.

THIS REQUIRES THAT A TEST PROGRAM BE ESTABLISHED THAT ASSURES THAT TESTING BE PERFORMED IN ACCORDANCE WITH WRITTEN TESTS PROCEDURES WHICH INCORPORATE LIMITS CONTAINED IN THE DESIGN DOCUMENTS.

OTHER RECENT SYSTEMS IN WHICH FLOW PROBLEMS HAVE BEEN FOUND ARE CCW, AFW, AND LPSI. 4 1

FOLI.0WUP:

THE REGION WILL REQUIRE THAT SERVICE WATER FLOW IS DEMONSTRATED TO BE ADEQUATE PRIOR TO RESTART.

POINT BEACH 2 - BOTH MSIVs FAIL TO CLOSE~ FULLY ON MANUAL DEMAND SEPTEMBER 28, 1986 - (VERN H0DGE, IE)

PROBLEM: BOTH MSIVs REQUIRED MANUAL ASSISTANCE TO FULLY CLOSE DURING NORMAL PLANT SHUTDOWN CAUSE: SUSPECT PACKING T00 TIGHT; VALVES WILL BE DISASSEMBLED NEXT WEEK SIGNIFICANCE:

DEGRADATION IN MAIN STEAM ISOLATION SYSTEM CIRCUMSTANCES:

UNIT 2 WAS SHUTTING DOWN FOR REFUELING (7 WEEKS), USING NORMAL PROCEDURES. ON MANUAL SIGNAL FROM CONTROL ROOM, BOTH VALVES CLOSED BUT NOT FULLY. PISTONS IN AIR CYLINDERS WERE TAPPED IN WITH MALLET TO CLOSE THE VALVES.

TWO YEARS AG0, UNIT 2 VALVES WERE BROKEN DOWN AND REPACKED, PERHAPS T00 TIGHTLY.

THE 12/31/85 TRIP SAW THE B MSIV FAIL TO CLOSE ON MANUAL DEMAND. HOWEVER, BEFORE STARTUP, IT WAS REPAIRED BY LOOSEN-ING THE PACKING AND T!!EN TESTED SUCCESSFULLY.

UNIT 1 IS OPERATING AT FULL POWER. ITS MSIVs HAVE BEEN SUCCESSFULLY TESTED SEVERAL TIMES IN RECENT MONTHS.

FOLLOWUP:

LICENSEE WILL DISASSEMBLE, DETERMINE ROOT CAUSE, REPAIR AND TEST NEXT WEEK. VEND 0R REP (ATWOOD-MORRILL) WILL BE PRESENT.

IE WILL KEEP INFORMED REGARDING THE RESULTS OF THE LICENSEE'S EVALUATION AND DETERMINE THE NEED FOR AN INFORMATION NOTICE.

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WNP N0 ANALYSIS OF P0TENTIAL FLOODING DUE TO FIRE MAIN BREAKS AUGUST 19, 1986 - JOHN 0. BRADFUTE, NRR PROBLEM:

NO FLOODING ANALYSIS CONDUCTED FOR WET-SPRINKLER SYSTEM ADDED TO CONTROL ROOM COMPLEX N0 FLOODING ANALYSES EVER CONDUCTED FOR FIVE OTHER AREAS OUTSIDE REACTOR BUILDING AND CONTAINING SAFETY RELATED EQUIPMENT CAUSE:.

OVERSIGHT DURING DESIGN OF CONTROL ROOM COMPLEX SPRINKLER SYSTEM BURNS AND ROE FAILED TO COMPLETE ANALYSES IN 1983 (BURNS AND ROE COMPLETED FLOODING ANALYSES FOR REACTOR BUILDING)

SIGNIFICANCE:

FLOOD IN CONTROL ROOM FROM ADJOINING AREAS COULD PREVENT PLANT SHUTDOWN FROM CONTROL ROOM

- NO DRAINS

- CABLING UNDER FLOOR

- PROCEDURES CHANGED TO EVACUATE CONTROL ROOM IN EVENT OF FLOODING

- REMOTE SHUTDOWN PANEL CABLING INDEPENDENT OF CONTROL ROOM CABLING

- SAFE SHUTDOWN FROM REMOTE SHUTDOWN PANEL IS ASSURED PRELIMINARY EVALUATIONS OF OTHER AREAS INDICATE-FLOODING WILL NOT ENDANGER EQUIPMENT ESSENTIAL FOR SAFE SHUTDOWN CONCLUSION - THE PUBLIC IS NOT AT RISK DISCUSSION:

AREAS AFFECTED:

- CONTROL ROOM (IN RAD WASTE BUILDING)

- CABLE SPREADING ROOM (IN RAD WASTE BUILDING)

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- $MERGENCY AIR HANDLING ROOM (IN RAD WASTE BUILDING)

- CRITICAL SWITCH GEAR ROOM (IN RAD WASTE BUILDING)

- DIESEL GENERATOR BUILDING

- STANDBY SERVICE WATER PUMP HOUSE SUPPLY SYSTEM ACTION:

- WALKED DOWN ALL AFFECTED AREAS FOR FLOODING THREATS

- DETERMINED THAT THERE WAS N0 THREAT TO ELECTRICAL EQUIPMENT EXCEPT IN CONTROL ROOM

- SHUT OFF WATER TO CONTROL ROOM SYSTEM

- DETERMINED THAT SAFETY SHUTDOWN IS ASSURED FROM THE REMOTE SHUTDOWN PANEL

- INSTITUTED ONE HOUR FIRE WATCH IN CONTROL ROOM AND INSTALLED FIRE EXTINGUISHERS FOLLOW-UP CONTINUE MORE DETAILED ANALYSIS

- EXAMINE EACH FIRE PROTECTION SYSTEM PIPE

- DOCUMENT FLOODING THREAT

- REFINE ANALYSIS TO DETERMINE FLOODING RATE

- SUPPLEMENT LER WITH SCHEDULE COMPLETE DETAILED ANALYSIS BY NOVEMBER 21, 1986 COMPLETE INDEPENDENT VERIFICATION BY FEBRUARY 1987

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OTHER EVENTS OF INTEREST

< OYSTER CREEK, - CONTROL R0D DRIVE ilYDRAULICCONTROLUNITS(HCU)NOTINSTALLED AS DESIGNED AUGUST 28, 1986 - (R. BECKER, NRR)

PROBLEM: 80 0F 137 CONTROL ROD DRIVE (CRD) HCUs WERE NOT INSTALLED AS DESIGED AND NOT SEISMICALLY QUALIFIED CAUSE: INSTALLATION FIELD CHANGE NOT INCORPORATED INTO DESIGN DRAWINGS OR ANALYZED FOR SEISMIC QUALIFICATIONS DURING ORIGINAL PLANT CONSTRUCTION SIGNIFICANCE:

IF AN OBE (0.11G) OCCURRED, P01ENTIAL FOR DAMAGING AND DISABLING A LARGE FRACTION OF CRD-HCUS AND POSSIBLY SMALL BREAK LOCAS IN SECONDARY CONTAIWENT DISCUSSION:

DURING I E BULLETIN 79-02 IPPLEENTATION INSKCTION, RESIDENT INSPECTOR NOTED INSTALLATION DISPARITY - APRIL 86 SOE HCU ANCHORS WERE WELDED RATHER THAN BOLTED AS DESIGNED ANALYSIS DONE ON WELDED INSTALLATION DETERMINED WELDED INSTALLATION DID NOT E ET SEISMIC CLASS I DESIGN REQUIREE NTS - AUGUST 28, 1986 - UNIT IN OUTAGE DOClfENTATION TRACEABILITY LOST-CORRECTION C0FPLETED (80 UNITS BOLTED) DURING CURRENT OUTAGE FOLLOW UP:

REGION FOLLOWING PLANT ACTION MODIFICATION COELETE

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REACTOR SCRAM

SUMMARY

WEEK ENDING 10/05/G6 I. PLANT SPECIFIC DATA DATE -SITE UNIT POWER RPS CAUSE COMPLI- YTD YTD YTD CATIONS ABOVE BELOW TOTAL 15% 15%

09/29/86 PEACH BOTTOM 2 30 M EQUIPMENT NO 4 09/30/86 LYRON 0 4 1 93 A FERSONNEL -

lO N 4 0 4 10/02/96 BYRON 1 3M FERSONNEL NO

' 4 1 5 10/04/06 MONTICELLO 1 62 A EQUIP / MECH. NO 1 0 1 10/04/06 YANVEE ROWE 1 100 A EQUIP / MECH. NO 2 10/04/06 VERMONT YANKEE 0 2 1 1A UNKNOWN NO O 2 2 30/05/S6 FERMI 15 M . EQUIP / MECH. NO O ~2 2 e

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1 II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES

. SCRAME FOR WEEK ENDING

, 10/05/86  ;

SCRAM CAUSE FOWER '

NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE

, YTD (3) (4) o* POWER >15%

EQUIP. RELATED >15% 3 4.8 5.4 (68%)

PERS. RELATED(6) >15% 1 1.9 2.0 (25%)

CTHER(7) ->15% 0 0.6 0.6 ( 7%)

• • Subtotal **

4 7.3 8.0 o* POWER <15%

EQUIP. RELATED <15% 1 1.5 1.3 (54%)

PERS. RELATED <15% 1 0.9 0.9 (38%)

i OTHER <15% 1 0.2 0.2 ( 8%)

ed Subtotal **

3 2.6 '

2.4

• • • Total *** -

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10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVEi(AGE AVERAGE YTD MANUAL SCRAMS 3 1.1 1.0 AUTOMATIC SCRAMS 4 8.8 9.4 l

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. l NOTES ,

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l 1 -- PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCPAMS ARE DEFINED AS REACTOR PROTECTIVE 4

ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE i i WITH A PLANT PROCEDURE.

E.

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 MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL 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.

l 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 CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.

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Page No. 1

' 10/06/96 SIGNIFICANT EVENTS FREQUENCY PERFORMANCE INDICATOR Nc. 4-PLC]T'AMEN EVENT EVENT IESCRIPTION SIGNIFICANCE QTR DATE PDINT BEACH 2 09/28/86 BOTH M31Vs FAIL TO CLOSE FULLY ON MANUAL DEMAND. PDTENTIAL FOR OR ACTUAL DEGREDATION OF 1 MSIVs CLOSED WITH MANUAL ASSISTANCE. SAFETY-RELATED EQUIPMENT PALISALES 1 07/30/06 SERVICE WATER PUMPS DO N3T MEET FSAR FLOW POTENTIAL FOR OR ACTUAL CEGREDATION OF 1-REGUIREMENTS. aFPARENTLY DUE TO NOT BACKFITTINS SAFETY-RELATED EQUIPMENT FROFER IMPELLER.

WNP 2 08/17/86 N3 ANALYSIS WAS PERFORMED OF FDTENTIAL FLOODING IDENTIFICATION OF SAFETY-SIGNIFICANT CONDITION 1 DUE TO FIRE MAIN BREAKS WHEN SPRINKLER SYSTEM NOT CONSIIEEED IN LICENSINS BASIS ~

WAS A!DED TO ROOMS ADJACENT TO CONTRO. ROOM.

OCONEE 2 10/01/96 LOSS OF LOW PRESSURE SERVICE WATER DL'E TO AIR FOTENTIAL FOR OR ACTUAL DEEREIATION 0F 1 INLEAKA3E ON CONDENSUR CIRCULATINS WATER PUMP SAFETY-RELATED EQUlFMEhi FLANSE.

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ENCLOSURE 3.

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$le No[ t Ig/01/B0

g. OPERATINS REACTORS EVENTS MEETING FOLLOWUP ITEMS

- F+ l AS OF MEETING B6-35 DN OCTOBER 6, 1986 Y. (IN ASCENDING MEETING DATE, NSSS VEND 0R, FACILITY ORDER) h-.

s l DID FAtlllTY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS I BOERI NSSS VENDOR / DIVISION / COMPLET. BY DOCUMENT, I ING EVENT DESCRIP. INDIVIDUAL DATE(S) MEETING,ETC.

l TE I?

lh-10 OYSTER CREEK NRR /HDUSTON W RESQLVE THE QUESTION OF THE 10/30/86 DPEN / / FDLLOWUP ACTION TO g31/86 SE / LEVEL / ACCEPTABILITY OF BLIND SWITCHES / / BE INCORPORATED IN t'a SWITCH SETPOINT AND DELETION OF DAILY CHANNEL / / REVIEW 0F JUNE 1,1966 EVENT AT yh DRIFT CHECK

. LASSALLE

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I h21 VERMONT YANKEE NRR /HOLAHAN 6. DETERMINE STATUS AND 10/30/86 DPEN / /

I p/B6 GE / PROBLEMS / EFFECTIVENESS OF STAFF AND 09/!0/86

~ LICENSEE ACTION ON / /

WITHSCRAM

[f- SOLENDID VALVES POST-MAINTENANCE TESTING (GL g '

B3-28). DEVELOP RECOMMENDATIONS i FOR FURTHER ACTION 4*

.I h;23 MULTI NRR / HOUSTON W. DETERMINE APPROPRIATE 10/30/86 CLOSED 10/06/86 7/07/86 NA / / RESULATORY REQUIREMENTS PASED 09/30/06 JULY 24,1996 2.1 BWRS-RESIDUAL ON RECOMMENDATIONS O!SCUSSED AT / / MEMD R.HERMANN

% HEAT REMOVAL BRIEFING TO 6. LAINAS h- PUMP / WEAR RING k' FAILURES -

@c FDLLOWUP 06-28 6 RAND SULF IE / JORDAN E. ASSESS PDTENTIAL FOR SENERIC 10/30/86 OPEN / / INFDRPATIZ N:TICE

[B/11/86 6E / CONTROL RDO / APPLICABILITY 09/30/86 IN PREFARATION "4 WITHDRAWAL / /

h PROBLEM N-32 NINE MILE PT 1 NRR /RDSA F. DISCUSS WITH LICENSEE AND 10/24/B6 OPEN / /

99/15/B6 6E / SCRAM NRR /ZWOLINSKI J. REB 10N LICENSEE'S / /

h OUTLET VALVE IMPLEMENTATION OF GL 63-28 IN / /

EEFERENCE TO 09/08/26 EVENT fd DIAPHERAM FAILURE if Elle has been deleted.

y - . - ,-. _ . - , , _ . - - - - - . _ _ . . -_