ML20036C172

Summary of 930520 Meeting W/Util Representatives at Plants to Discuss Status of Current Licensing Activities for Plants.List of Attendees,Meeting Agenda & Viewgraphs Encl

ML20036C172
Person / Time
Site:	Hatch, Vogtle
Issue date:	06/07/1993
From:	Jabbour K Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9306150103
Download: ML20036C172 (37)

Text

{{#Wiki_filter:( 9 *E% d_9 i 4 UNITED STATES ~ j NUCLEAR REGULATORY COMMISSION r f WASHINGTON, D.C. 20555-0001

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June 7,1993 Docket Nos. 50-321, 50-366 and 50-424, 50-425 LICENSEE: Georgia Power Company, et al. FACILITY: Hatch Nuclear Plant, Units.1 and 2 Vogtle Nuclear Plant, Units 1 and 2

SUMMARY

OF MAY 20, 1993, MEETING WITH GEORGIA POWER COMPANY ON LICENSING ISSUES - HATCH AND V0GTLE NUCLEAR PLANTS Introduction On May 20, 1993, the NRC staff met with Georgia Power Company (GPC or licensee) representatives at Plant Hatch, Baxley, Georgia, to discuss the status of current licensing activities.for the Hatch and Vogtle plants. lists the attendees and Enclosure 2 contains the meeting agenda. Discussion After brief introductory remarks by NRC and GPC regarding the objectives of the meeting, Mr. L. Sumner, GPC, discussed the status of Plant Hatch. He stated that Hatch Unit I was maintaining 100% rated thermal power without any major problems. Hatch Unit 2 was maintaining 74% rated thermal power because of fuel considerations. GPC was evaluating Unit 2 operation, in consultation with General Electric, to determine if an increase in power level is appropriate. The viewgraph used for Mr. Sumner's presentation is included as. Mr. P. Roberts, GPC, discussed.the recent Hatch Units 1 and 2 refueling / maintenance outages. He stated that the Unit 1 outage la'sted 61 days and the total exposure was 414 person-rem; for Unit 2, the outage lasted 67 days and the total exposure was 369 person-rem. Both units completed the installation of their containment hardened vents and the performance of their-integrated leak rate tests. Furthermore, he discussed the major accomplishments of both units during their respective outages, as well as the recent Unit 2 forced outage (i.e., 35 day duration) associated with the leaking fuel. The viewgraphs used for his presentation are included as'. Mr. S. Bethay, GPC, discussed the process used by GPC for the-individual plant examination (IPE) of severe accidents at Hatch. The organizations involved were: (1) Hatch site personnel from engineering, training,'and operations, (2) Birmingham project personnel from licensing and engineering, and (3) Southern Nuclear Company Technical Services personnel. Furthermore,.he discussed the scope and results of the Hatch IPE evaluation. The total core damage frequencies were determined to be 2.1E-05 events / year for Unit ~1tand 2.2E-05 events / year for Unit 2. The-licensee identified the differences j between Units 1 and 2, and their estimated impact on core damage frequencies. J Mr. Bethay also discussed the schedule for the Hatch Technical Specifications jj '4M I,_mf.m epy ki

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\\ t June 7, 1993 (TS) Improvement Program. He stated that GPC plans to submit its proposed changes to NRC on November 12, 1993, and will request approval in the May/ June 1994 timeframe. The licensee plans to implement the new TS at plant Hatch May 31, 1995. The viewgraphs used for his presentation are included as. Mr. S. Chestnut, GPC, discussed the operating status of Plant Vogtle, Vogtle Unit 1 outage activities, outage risk management, Generic Letter 89-10 program, and the Vogtle Unit 2 outage schedule. He stated that the recent Unit 1 outage lasted 45 days and Unit 2 outage is scheduled to last 35 days beginning September 11, 1993. Furthermore, he discussed the IPE results including the contribution of initiating events for Vogtle Units 1 and 2. The total core damage frequency for each Vogtle unit was determined to be 4.87E-05 events / year. The viewgraphs used for his presentation are included as. Mr. K. Jabbour, NRC, discussed the procedure for NRC enforcement actions published in the Federal Reaister (58 FR 14308 through 14310) dated March 17, 1993. He stated that the Commission has determined that a discussion of the possibility of enforcement discretion should be placed in Section VII of the Enforcement Policy. In each case where the NRC staff has decided to exercise its enforcement discretion, enforcement action may be taken for the root cause that led to the noncompliance issue. Furthermore, licensees who request enforcement discretion should document the safety basis for the request including an evaluation of the safety significance and the potential consequences of the proposed course of action, a description of compensatory measures, a justification for the duration of the request, the basis for the licensees' conclusion that the request does not have a potential adverse impact on public health and safety, and does not involve adverse consequences to the environment, and any other information needed by the NRC staff before making a decision to exercise discretion. Conclusion At the conclusion of the meeting, the NRC staff and GPC representatives agreed to have the next meeting in Rockville, Maryland, either in late summer or early fall of 1993. /s/ Kahtan N. Jabbour, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 1. List of Attendees 2. Meeting Agenda 3.- 6. Viewgraphs DISTRIBUTION: SEE NEXT PAGE cc w/ enclosures: G:\\HATCHp T E RFAC.MTS See next page DOCUMENT NAME: s PDil-3:L ) PDi l-3 : PM ;(tM PDIl-3:PM D I k 3 BERRY k KJABBOUR:cw DHOOD 3d// D 1 THEWS /%/93 6 /0 1/93 (, / /93 /93 7

9 June 7, 1993 -l ) (TS) Improvement Program. He stated that GPC plans to submit its proposed changes to NRC on November 12, 1993, and will request approval in the May/ June 1994 timeframe. The licensee plans to implement the new TS at plant Hatch May 31, 1995. The viewgraphs used for his presentation are included as. .l Mr. S. Chestnut, GPC, discussed the operating status of Plant Vogtle, Vogtle Unit l' outage activities, outage risk management, Generic letter 89-10 program, and the Vogtle Unit 2 outage schedule. He stated that the recent -l Unit 1 outage lasted 45 days and Unit 2 outage i.s scheduled to last 35 days beginning September 11, 1993. Furthermore, he-discussed the IPE results inclu' ding the contribution of initiating events for Vogtle Units 1 and 2. The total core damage frequency for each Vogtle unit was determined to be 4.87E-05 events / year. The viewgraphs used for his presentation are included as Mr. K. Jabbour, NRC, discussed the procedure for NRC enforcement actions published in the Federal Register (58 FR 14308 through 14310) dated March 17, 1993. He stated that the Commission has determined that a t discussion of the possibility of-enforcement discretion should be placed in i Section V11 of the Enforcement Policy. In each case where the NRC staff has decided to exercise its enforcement discretion, enforcement action may be taken for the root -cause _that led to the noncompliance issue. Furthermore, licensees who request enforcement discretion should document the safety basis for the request including an evaluation of the safety significance and the potential consequences of the proposed course of action, a description of 1 compensatory measures, a justification for the duration of the request, the basis for the licensees' conclusion that the request does not have a potential adverse impact on public health and safety, and does not involve adverse i consequences to the environment, and any other information needed by the NRC i staff before making a decision to exercise discretion. Conclusion At'the conclusion of the meeting, the JRC staff and GPC representatives agreed I to have the next meeting in Rockvi'ie, Maryland, either in late summer or. early fall of 1993. i i J Kahtan N. Jabbour, Project Manager i Project Directorate II-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Enclosures:

1. List of Attendees

2..

Meeting Agenda 3.- 6. Viewgraphs cc w/ enclosures: See next page

Edwin I. Hatch Nuclear Plant Georgia Power Company Vogtle Electric Generating Plant l CC Mr. Ernest L. Blake, Jr. Mr. R. P. Mcdonald Shaw, Pittman, Potts and Trowbridge Executive Vice President - f 2300 N Street, NW. Nuclear Operations Washington, DC 20037 Georgia Power Company P. O. Box 1295 Mr. J. T. Beckham Birmingham, Alabama 35201 ~ Vice President - Plant Hatch Georgia Power Company Mr. Alan R. Herdt, Chief P. O. Box 1295 Project Branch-#3 Birmingham, Alabama 35201 U. S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Mr. S. J. Bethay Atlanta, Georgia 30323 Manager Licensing - Hatch l Georgia Power Company Mr. Dan Smith i P. O. Box 1295 Power Supply Operations Birmingham, Alabama 35201 Oglethorpe Power Corporation 2100 East Exchange Place Mr. L. Sumner Turker, Georgia 30085-1349 General Manager, Nuclear Plant Georgia Power Company Charles A. Patrizia, Esquire Route 1, Box 439 Paul, Hastings Janofsky & Walker. Baxley, Georgia 31513 12th Floor i 1050 Connecticut Avenue, NW. Resident Inspector Washington, DC 20036 U. S. Nuclear Regulatory Commission Route 1, Box 725 + Baxley, Georgia 31513 i Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 Mr. Charles H. Badger Office of Planning and Budget Room 610 270 Washington Street, SW. i' Atlanta, Georgia 30334 Harold Reheis, Director ~ Department of Natural Resources 205 Butler Street, SE., Suite 1252 ' i Atlanta, Georgia 30334 Chairman Appling County Commissioners County Courthouse Baxley, Georgia 31513 i 'f'5 H w: is m a 9 m a ww =

.i Edwin I. Hatch Nuclear Plant' Georgia Power Company Vogtle Generating Plant j CC" Mr. J. A. Bailey Office of the County Commissioner Manager -Licensing Burke County Commission Georgia Power Company Waynesboro, Georgia 30830. m P. O. Box 1295 Birmingham, Alabama 35201 Resident Inspector i U. S. Nuclear Regulatory ' Commission Mr. W. B. Shipman P. O. Box 572 ~. General Manager, Vogtle Electric Waynesboro, Georgia 30830 Generating Plant P. O. Box 1600 Waynesboro, Georgia 30830 Office of Planning and budget Room 615B 270 Washington Street, SW. l Atlanta, Georgia 30334 Mr. C. K. McCoy Vice President - Nuclear Vogtle Project Georgia Power Company P. O. Box 1295 't Birmingham, Alabama 35201 Attorney General Law Department. j 132 Judicial Building Atlanta, Georgia 30334 Art Domby, Esquire i Troutman, Sanders 600 Peachtree Street. i Nations Bank Plaza Suite 5200 Atlanta, Georgia 30308-2210 Mr. W. G. Hairston, III Senior Vice President - Nuclear Operations Georgia Power Company P. O. Box 1295 Birmingham, Alabama 35201 i l

June 7,1993 l _ DISTRIBUTION-l Docket fileN NRC & Local PDRs PDII-3 R/F T. Murley/F. Miraglia,12G18 J. Partlow,12G18 S. Varga G. Lainas D. Matthews 4 I L. Berry OGC, 15B18 E. Jordan, MNBB3701 K. Jabbour ACRS (10), P-315 L. Plisco, EDO,17G21 E. Merschoff, RII D. Hood A. Herdt, RII L. Wert, RII B. Bonser, RII I .110050

s ENCLOSURE 1 May 20. 1993 NRC/GPC Meetino list of Attendees j NRC GPC i K. Jabbour L. Sumner l D. Hood J. Heidt A. Herdt D. Read L. Wert S. Tipps. B. Bonser S. Bethay P. Roberts S. Chestnut J. Bailey M. Sheibani H. Dougherty (Oglethorpo) ( f f I L h

ENCLOSURE 2 AGENDA NRC/GPC Interface Meetina May 20. 1993 I. Introduction NRC/GPC II. Plant Hatch Operations and GPC Outages Review

• IPE Results
• Improved Tech Specs Schedule III.

Plant Vogtle Operations and GPC Outages Review IV. NRC Presentation NRC V. Breakout Sessions on Outstanding NRC/GPC Licensing Issues I VI. Closing Comments NRC/GPC

ENCLOSURE 3 .i l PLANT STATUS 5/20/93 i I UNIT 1: MAINTAINING 100 % RATED THERMAL POWER ; 780 MWE 3 DAYS ON LINE NO MAJOR PROBLEMS UNIT 2: MAINTAINING 74 % RATED THERMAL POWER ; 587 MWE { 43 DAYS ON LINE l l AT REDUCED LOAD DUE TO FUEL CONSIDERATIONS i ~ EVALUATING UNIT OPERATION TO DETERMINE IF AN INCREASE IN POWER IS APPROPRIATE NO OTHER MAJOR PROBLEMS ~ 1 '1 NRC Interface M:cting 5/20/93 l

ENCLOSURE 4 1992 UNIT 2 1 TENTH REFUELING OUTAGE o OVERVIEW I OFF LINE SEPTEMBER 16 ON LINE NOVEMBER 21 OUTAGE DURATION 66.7 DAYS o

SUMMARY

COMPLETED 2914 WORK ORDERS (MWOS) IMPLEMENTED 68 PLANT MODIFICATIONS (DCRS) I RECEIVED 369 TOTAL MAN-REM 1 i j l - NRC Interface Meeting 05/20/93

1992 UNIT 2 1 TENTH REFUELING OUTAGE MAJOR ACCOMPLISHMENTS DISASSEMBLED / REASSEMBLED REACTOR PRESSURE VESSEL & REFUELED FOR 18-MONTH CYCLE (WITH FULL CORE OFF LOAD / RELOAD) COMPLETED DEBRIS INSPECTION ON ALL RELOAD FUEL ASSEMBLIES SIPPED ENTIRE CORE & IDENTIFIED 3 " LEAKERS" PERFORMED AN INTEGRATED LEAK RATE TEST (ILRT) REPLACED 2A & 2C EDG BATTERY CHARGERS REPLACED IB EDG CYLINDER LINERS,0-RINGS, PISTONS, BATTERIES & CHARGERS REFURBISHED TIP MACHINES COMPLETED HPCI & RCIC SYSTEM UPGRADES DISASSEMBLED & INSPECTED 'A' LP TURBINE COMPLETED 177 INITIAL LOCAL LEAK RATE TESTS (LLRTS) ON VALVES WITH ONLY 21 FAILURES REPLACED 24 CONTROL ROD BLADES & 4 LOCAL POWER RANGE MONITORS COMPLETED OVER 50 MOTOR-OPERATED VALVE TESTS UTILIZING VOTES EQUIPMENT INSTALLED CONTAINMENT HARDENED VENT MODIFICATION PERFORMED I&C TIME RESPONSE TESTING l NRCInterface Meeting 05/20/93

1993 3 UNIT 1 FOURTEENTH REFUELING OUTAGE o OVERVIEW OFF LINE MARCH 16 ON LINE MAY 16 OUTAGE DURATION 61.2 DAYS o

SUMMARY

COMPLETED 2524 WORK ORDERS (MWOS IMPLEMENTED 62 PLANT MODIFICATIONS (DCRS) RECEIVED 414 TOTAL MAN-REM i I ) NRC Interface Meeting 05/20/93

1993 UNIT 1 FOURTEENTH REFUELING OUTAGE MAJOR ACCOMPLISH.MENTS DISASSEMBLED / REASSEMBLED REACTOR PRESSURE VESSEL & REFUELED FOR 18-MONTH CYCLE (WITH FULL CORE OFFLOAD / RELOAD) COMPLETED ROUTINE FUEL INSPECTION AND LIMITED DEBRIS INSPECTION REPLACED BOTH SHROUD ACCESS HOLE COVERS PERFORMED AN INTEGRATED LEAK RATE TEST (ILRT) REPLACED ALL STATION SERVICE BATTERIES PERFORMED MECHANICAL STRESS IMPROVEMENT PROCESS (MSIP) ON 29 IGSCC SUSCEPTIBLE WELDS INSTALLED AND UTILIZED AN ALTERNATE FUEL POOL COOLING SYSTEM. REPLACED 1A & IC EDG CYLINDER LINERS,0-RINGS & PISTONS PERFORMED EXTENSIVE MAIN GENERATOR & HP TURBINE PMS COMPLETED 152 INITIAL LLRTS ON VALVES WITH ONLY 12 FAILURES REPLACED 20 CONTROL ROD DRIVES,18 CONTROL ROD BLADES AND 5 LPRMs PERFORMED OVER 50 MOTOR-OPERATED VALVE TESTS UTILIZING VOTES EQUIPMENT INSTALLED TAPS FOR RWL INSTRUMENTATION KEEP-FILL FROM CRD INSPECTED, DESLUDGED, AND SPOT-COATED TORUS INSTALLED CONTAINMENT HARDENED VENT MODIFICATION NRC Interface Meeting 05/20/93

UNIT 2 FORCED OUTAGE FOR LEAKING FUEL GENERATOR OFF LINE 3/03/93 TOTAL DURATION: 34.6 DAYS GENERATOR ON LINE 4/06/93 MAJOR ACCOMPLISIIMENTS SIPPED ALL 560 FUEL ASSEMBLIES INSPECTED 358 FUEL ASSEMBLIES FOUND 46 FUEL ASSEMBLIES WITH DEBRIS REPLACED 4 FUEL ASSEMBLIES BALANCED 'B' REACTOR FEED PUMP TURBINE ROTOR REPAIRED 'D' TIP MACHINE NRC Interface Meetmg 5/20/93

ENCLOSURE 5 l ORGANIZATION INVOLVEMENT l SLTE ENGINEERING i TRAINING OPERATIONS IRG t-PROJECT LICENSING IRG TECHNICAL SERVICES

i I i r PLANT HATCH EVALUATION RESULTS TOTAL CORE DAMAGE FREQUENCIES ARE: 2.1E-05 EVENTS / YEAR (UNIT 1). 2.2E-05 EVENTS / YEAR (UNIT 2). .I NO VULNERABILITIES WERE IDENTIFIED. i i k i s ,I i s i i

L ~ EVALUATION SCOPE EXAMINES CORE DAMAGE AND CONTAINMENT PERFORMANCE. EXAMINES INTERNAL EVENTS FROM > 35% POWER 1 (INCLUDING LOSP AND INTERNAL FLOODING). HAS A MISSION TIME OF 24 HOURS FOR LEVEL i AND 40 HOURS FOR LEVEL 11. DOES NOT EXAMINE SHUTDOWN RISK, SEISMIC, FIRE, AND INTERNAL SABOTAGE. TAKES CREDIT FOR TRADITIONAL SAFETY-RELATED, AS WELL AS NONSAFETY-RELATED, EQUIPMENT. GOES BEYOND SINGLE-FAILURE CRITERIA AND DESIGN BASIS ACCIDENTS. SYSTEMATICALLY ACCOUNTS FOR SUPPORT SYSTEM DEPENDENCIES. L

j e RISK-SIGNIFICANT DIFFERENCES BETWEEN PLANT HATCH UNITS 1 AND 2 i Estimated Impact on CDF I i Unit 1 Unit 2 l 1. The initiating event frequencies for frequent transients 6% were slightly different. 2. Unit 2 has a separate chilled water system which <4% <1% I supplies the drywell coolers. 3. Diesel 1B is normally aligned to Unit 1. <1% l 4. Loss of 1R24-S037 (from 600-V bus 1 D) causes <1% the service air compressor discharge valves i to fail closed. Similar valves for Unit 2 fail open. 5. The MCR chillers and AHUs are supported by Unit 1 <1% electrical power 9 6. Diesel 18 depends on Unit 1600-V AC power for <1% its two dedicated fuel oil transfer pumps. 7. Unit 2 diesels have a 3-day LCO, while Unit 1 <1% diesels have a 7-day LCO. l f 8. Other differences... <1% ' <1% 1

. a. PROCEDURAL AND HARDWARE MODIFICATIONS FOR WHICH CREDIT IS TAKEN HARDENED VENT UNIT 1 PSW DISCHARGE VALVE F363 CONTROL BUILDING HVAC MCR HVAC INTAKE STRUCTURE HVAC RHR/CS CORNER ROOM COOLING RHRSW MOTOR COOLING e SBO MODIFICATIONS r i i

j., ' ',:.

Class E Class IA 6 T2E4 p2.5%) I Class M [ 4 04E4103) $ 41 Ctess illC . Claes Inc 4 75Eos (23 os) 7 4 M MM) / 4.23E46 (19.5%) l Csase m 10*E-F MSN -- Cson Ic 1MF M8%) N Class V Class a 1.7tE-7 p8%) Class V me pen) ClassilI8 N 1.77E-7 PM) 3.52E-6 (16.2%) Class iv U '" 4 e.gq C$ses ID . E 7 (1.8%) S$*j'ian) SUI p.s%) CORE DAMAGE FREQUENCY BY ACCIDENT CLASS IA Transient with loss of all high pressure inlec"on and failure to depressurize IB Station Blackout IC ATWS with loss ofinjection ID Transient with loss of low pressure injecto a ll Loss of all decay heat remova! IllB LOCA with loss of high pressure injection and failure to depressurize IllC LOCA with loss of low pressure injection IV ATWS with containment overpressurization followed by loss of injection V Unisolated LOCA outside containment (containment bypass) l

e-s Electncal Support Electncal Support System initiators System initiators 6 70L4 02 43) 6W @ W Loss of Offsite Power 64 8%) 5M6mW ,77, //// ,/O Intemal floods ///// / intemal Floods 3 33E4 (0 2%) /,/ 3 40E4 (0 2%) / '/N/

• - - ATWS Events

/j ' ~ - ATWS Events ' /,e 6 37E-7 (2 7%) '/j ,/ e / 50'07(25%) y/' /, -- \\ s N //,. 'Q'//).:, 'N \\ N ~ b LOCA Events \\ ' LOCA Events x, 8 61L-7 (4 0%) Transients 8 41E-7 (4 t%) Loss of Offsite Power 519E 4 (251%) 51004(235%) M nhanical Support Mechanical Support System intiators System intiators 2 07E 6 (9 5%) 2 04E-6 (9 7%) Unit 1 Core Damage Frequency = 2.2E-5 events / year Unit 2 Core Damage Frequency = 2.1E-5 events / year CORE DAMAGE FREQUENCY BY INITIATING EVENT GROUP ^ Electrical Support Mechanical Support Transients System initiators System intiators LOCA Events ATWS Events Inatwrtent Opensng MSN Charane Loss of Feedwater loss of an AC Bus Loss of PSW g, g,,,, y,j,, tms pawaso, MSiv Closuro Loss el a DC this Loss of MCR Coohng gg butw Irv Turtune Tnp toss of an SUT LOSSOf W I N "9 t oCAs outsuse Cnnt Beactor Scram AnotNws Loss of Condenstr Vacturn i 4

a. PLANT llATCll TEDNKH. S!YCFUliIDH Rffl0LDENT IT00IVR1 f ] start End m3 m4 MS l l l l issk Name Date Date 82 83 04 m 22 01 et et e2 Q M UtsIN ritIISS 25-Jart-93 l-Nou-93 m _..___t -._.__+--_.____4.______..__.._ F N L FfD m E E-Oct-93 12-Hau-93 b .____.+__~..k..--.-....4 ___-a ' M +. . _--.+.--y._..-v .. _ _ - g- _-i a PflC SUER 1l Tilt 12-nom 3 12-Nou-93 i.__.-.- . -... i -. -.. -, i. J _. +---4-_.. -. _ _ - + .___.___j _i _ _ _ .__.___.1-NHC MUU 12-Nou-93 20er94 W WEmuuuuuuuumu m EEE E

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i _4_ rnnnutt trtMINN 19-Jm-94 3ter95 ~ TRANNG Q-Nou-93 19-tier 95 ,. _____ _7 I .____._i M [MNT RLIDITED SPEE5 6-fetr45 3Hinry95 _ __ u W b 1 .n __._ g p 4_ MlutP FSm DWHIS 3-Jnri-95 30.-tiar-95 i m 5 d. Inu rnotIDUKs 6-est-94 3Htar95 + _ _ _ _. - (FHl. M1D eipiEN 3Hier95 3Hier95 j aj PRELIMINARY . ~.

ENCLOSURE 6 NRCINTERFACE MEETING MAY 20,1993 .f. AGENDA: . PLANT STATUS UNIT 1 OUTAGE ACTIVITIES . OUTAGE RISK MANAGEMENT . G.L. 89-10 PROGRAM UNIT 2 OUTAGE SCHEDULE e

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VOGTLE 1R4 COMPLETED ACTIVITIES l ......................u l = FUEL OFFLOAD, SHUFFLE AND RELOAD--INCLUDING RECONSTITUTION 1 = ILRT AND 80 LOCAL LEAK RATE TESTS l = POWER UPRATE = RCP MOTOR AND SEAL INSPECTIONS l = EDG 5 YEAR TEAR DOWN AND 18 MONTH SURV. = GL 89-10 IMPLEMENTATION 'MOV MODS AND DYNAMIC / STATIC TESTING r = SG SLUDGE LANCING = SG EDDY CURRENT TESTING (4 TUBES PLUGGED) = ESFAS TESTING

u. s_.a t 1R4 STATISTICS = OUTAGE START DATE 3/13/93 = OUTAGE FINISH DATE 4/27/93 = OUTAGE DURATION 45 DAYS = TOTAL ACTIVITIES SCHEDULED 3892 = TOTAL PM WORK ORDERS' 861' = TOTAL CORRECTIVE MWOs 1033 = TOTAL DESIGN CHANGES 46 ~ = TOTAL SURVEILLANCES 47.7 1 l l l '.

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• MOV MODIFICATION SCOPE:

-53 MODS-14 REPLACEMENTS -26 UNIT 1 OPERATORS REPLACED / MODIFIED DURING 1R4 27 UNIT 2 OPERATOR REPLACEMENTS / MODS DURING 2R3

• STATIC TESTING:

1 -TRANSITIONED FROM MOVATS TO VOTES 72 UNIT I VALVES TESTED DURING 1R4 APPROX. 60 UNIT 2 VALVES SCHEDULED DURING 2R3

• DYNAMIC TESTING:

4 16 TESTS PERFORMED DURING 1R4 I 16 TESTS SCHEDULED DURING 2R3 -e .w- - +.

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~ 2R3 STATISTICS (AS OF 5/18/93) = PROJECTED START DATE 9/11/93 = PROJECTED FINISH DATE 10/15/93 = PROJECTED DURATION 35 DAYS = TOTAL ACTIVITIES SCHEDULED 1970 = TOTAL PM WORK ORDERS 496 = TOTAL CORRECTIVE MWOs 308 = TOTAL DESIGN CHANGES 37 = TOTAL SURVEILLANCES 477 _________-__._-__._.___.._____,-_m.. m

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=s IPE RECOMMENDED PLANT AND PROCEDURE MODIFICATIONS o PROCEDURE ENHANCEMENT ALLOWING OPENING OF INVERTER ROOM DOORS ON LOSS OF CONTROL BUILDING ESF ELECTRICAL EQUIPMENT ROOM HVAC SYSTEM - PROCEDURE REVISION TO BE COMPLETED AT TIME OF SUBMITTAL t o PROCEDURE ENHANCEMENT TO ALLOW MANUAL CONTROL 0F AUXILIARY FEEDWATER i TURBINE-DRIVEN PUMP DURING LOSS OF ALL AC AND DC POWER - PROCEDURE REVISIOM TO BE COMPLETED AT TIME OF SUBMITTAL f 3 o PROCEDURE ENHANCEMENT TO ALLOW RESTORATION OF ONE NUCLEAR SERVICE l COOLING WATER (NSCW) PUMP TO OPERATION FOLLOWING LOSS OF NSCW - PROCEDURE REVISION TO BE COMPLETED AT TIME OF SUBMITTAL n

V b PLANT V0GTLE MAJOR RISK CONTRIBUTORS SYSTEMS LISTED IN ORDER OF IMPORTANCE TO THE IPE RESULTS o DIESEL GENERATORS 1 o AUXILIARY FEEDWATER I o NUCLEAR SERVICE COOLING WATER o CONTROL BUILDING ESF ELECTRICAL EQUIPMENT ROOM HVAC o CONDENSATE-FEED o ESSENTIAL CHILLED WATER l o CONTAINMENT FAN COOLING UNITS o COMPONENT COOLING WATER o ENGINEERED SAFETY FEATURE ACTUATION SYSTEM o CENTRIFUGAL CHARGING PUMPS o SAFETY INJECTION PUMPS o LOW PRESSURE INJECTION SYSTEM o 480V AC BUS A o NORMAL CHILL WATER o 125V DC BUSES l -l b

.t PLANT VOGTLE CORE DAMAGE FREQUENCY BY ACCIDENT CLASS CLASS IB 2.86E-6 (5.9%1 s + ht,~ ^ N 'N ~ CLASS litb g y '7,;,g. 4, 7, ',;- CLAStiIA 3.47E-G (7.1 %) f ig,,[ ~ } "j q, y,, 1.06E-5 (21.67%) Q gn- ', /, ' ^ L. J- ' 3 - s- ~~ 'Ll1;b(,s l' f + , a d ' ~. ( , s'. 1 n c',W g q '; ';' s ' ' r 'y '. f'>1 h 1,j'/',5 '8,' <,, ,^,s*, ,g 35 CLASS IIB m 1'Y I s ' '::: J , ' c 7 ' ; 1.82E-6 (3.7%) " Q d'f -{ e,' * , 3,', s ' 'a, ~ >--,,: Tj, s^ f 8' j * ',,' <3 w', ~ t s ',/;~ ., ' 1 as ' ~ 4 i AJ) c,,V if >-- vg{.,) < Q),:,, t - "r, - gg ,s 1; \\ a /,,1 ' [, CLASS lilA ~~ _, CLASS VB 2.60E-G (5.3%) "k: 1.33E-7 (0.3%) '~ 'n s ~~ -,r, - < CLASS VA 1.17E-7 (0.2%) CLASS IllB 1.50E-G (3.1 %) LASSIV i:siii 1.14E-7 (0.2%) CLASS lilC 1.98E-6 (4.1 %)

e xg:.

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s$ ifRi: CLASS IIA 1.68E-5 (34.6%) TOTAL CORE DAMAGE FREQUENCY = 4.87E-5 EVENTS / YEAR

]

f+

,?. - L PLANT VOGTLE CONTRIBUTION BY. INITIATING EVENT TOTAL CORE DAMAGE FREQUENCY' = 4.87E-5 EVENTS / YEAR 9 % @ ?!!& 2 h Adhhh.hhhh}V$M?ngsMWffyge.!$hhkkkk N@!MhfMb. as. % i@jytWtypY{^s@p@@Sp$$$p"$(+ J~MygfEh d Wr %g h ggM@gg lgg k M]gq[*E hgdfd L-LOSP/SBO -jj 3.39E-5 (69.8%) g fff k II$ ) j

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Map. . WW8)pw=' 3 6.' i>g n; -m.. u w. g h? M i ANM{j 'y gc " 30 p Mig kj:{% dfj ^

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g ! $ ' 3Qs shg I'gf$$ SPECIAL CASES y%;p$p{1M%~aMe & g* y{fjjffN!@ NN 2.4EJ (0.5%) ikihN8 4 v d 1- !!p4& g A -% kagy* Sh.4p$? ;k ~ hi b ( @h[..k *hhiEN 4gdgj{ls ~ ' O LOCA u".* M[h!s!kb. f,K k 9.24E-6 (19.2%) " hh hhg{f M s NISLOCAs 5.8E-8 (0.1 %) TRANSIENTS SGTR 3.3 E-6 (6.8%) - 1.7E-6 (3.6%) ~. - ~. - - ~ . -.. - - - - -. -.. -.. - - ~. - .. - ~ ~ - -. -.}}