ML20149J918

Summary of 871202 Meeting to Brief Director & Assistant Director for Region II Reactors in NRR on Util Operations. Meeting Attendee & Handout Encl

ML20149J918
Person / Time
Site:	Grand Gulf
Issue date:	02/19/1988
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8802230285
Download: ML20149J918 (40)

Text

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UNITED STATES NUCLE AR REGULATORY COMMISSION W AsHIN010N. D. C. 2055s a 4 g>- .j.

FE9 19 H1T 00:ket No. 50-416 LICENSEE: Syste- E*ergy Resour:es :n:.

FAC:LITY: Gran: Gulf Nv: lear Station, Unit 1 S UE.' E C T : 5'vv1;Y C CE EVEER 2, 19E7 WEETING REG C:N3 ERIE;;N3 0F NR; VANA3 EVENT CN GRAND GULF C; ERAT:CN Tre turpose of tre eeting was to Orief tre Cire:ter, Froje:t Dire:torate II-I 3ad t*e Assistant Dire:ter for Regien II ;eacters in NRR on Grard Gulf Nu: lear Stati:e (G3NS) ::erati:rs. En: 1:sur e ; is a list cf atten:ees at tre eetieg.

Er:::sure : is a ra ::.t ;re:are: ty Syste- Eree;> Res:s e :es, :":. f:r the eeetir;.

Tre licensee cescrited G3NS mana;e ent goals and methces used to a:nieve them (Sheeta 5-7 Encies re 2). Goals are set ea:n year for 40 plant cerforman:e indicaters, erfer ance reports are pre:are: conthly for Tanage ent use and re** r an:e enarts are p:ste: at are-: riate ' :stiens in t*e olant for e ;10)ees use. 5*eet 6 of En:1:sure 2 is a :erferracce surrary of sere key indicators. Cerfernance of ennagers in their area of responsibility is one of tre fatters used to determine salary ircreases. Regarding special improwe ent crea g:als (5 Feet 7), the staf f indicated that several plants are using an inte; rated livir; s:hedule li:ense cer:itien, in lieu of orders, to fix :: mit-

-art cates. T>e l':easee c:es s:Fedule plaat a:tiens for periods up to 5 yea *s A a .ill are su:P 5:ae:.'es a ailable t; t*e staff, .t :es *0; see a te e'it 1: sur; tae a l': ease : d'tica. Us.i: e ":ets ir 1955 mili :s :e s:'4:a:-

ing : Tart Oefi: 1e cy re: rting systems ar: plannir; outa;es. :NFO re::r e-:a-tiers regar:in; raintenance pre:ecures are teing censidered in the Fairtenar:e i pe:ve ert plan irpletentation, Nuclear plant engireerirg is perfor ed with 4 -*:use :e-s:-rel, eurect ': a fe. :: t-s::: e :' rye 4s in tre 3-es f i st a-rentatien are centro 15. Plant c;erati:ns, mainterar:e and te:nrical support evaluatiens are careir: 0.t Ourfr; ncreal c;erati:n with li:ensee perscanel es:e:t fer about 2E-53 :cetra:ter pers:enel in spe:iali:ed areas. Caring tre se:ced refuelirg outage, 750 centractor persennel .ere used in three snif ts.

Gran: Calf Nv: lear Station is fully a::redited by INFO. Sheets 5-11 of En:1c-sure 2 give a su- ary of INFO firciegs for 1957. Overall ;erferran:e is eie plary and no significant weairesses were n:te:, Regarcir; the fircing t*at a:diti:ral effert is 'eece: to rake te ::rary chaages per5 acent, the licensee state: nat nalf of t*e 56 cutstarcir; ite s woule te : pleted caring the se: re#uelie ',i:5 starte: N:se oer 6, l$E7, W rk a:tivities ar: li ersi"; a*tiCns Curir; t*.e se:Ord refuelin; cutage (5 02) a#e sP:=P 09 5*eet s 12-15 O f EP 10sure 2, As dis:ussed in preti:Us eet 9;s 4

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8802230295 GEh3219 PDR ADOCK 05000416 P PDR l

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with the staff, actions have Deen taken te minimi:e the potential for draining l the vessel during refueling ($neet 14) and for rapid closure of the primary con- l tainment in the event of a potential or actual radiation release in containment '

(Sheet 15). Regarding priority RF02 support a:tions (Sheet 18), the licensee i said the present outage s:tedule indicated a need fer changes to the Technical See:1fications (75) for the ATWS related systems and the reactor water cleanup (RWOU) systet by January 3, 1955. Ine staff said that the ccement eeriod in the Federal Register actice for these 75 changes would end January 4, 1953, and  !

that the RW:V Netice was provided opportunity for a prior hearing. Therefore, l the license amenc ent for the RWCU system TS changes could not be issued before i January 4; however, exigent cir:umstances for earlier issuance of the a enement  !

for ATWS related TS cnanges would be :ensicered. l t

Regarding major licensing activities in 1933 ($neet 19 of Enclosure 2), the  !

licensee said trat a EWR 0 ners Greup (Ea;03) is planning to complete the  !

i orove: EWR-6 Stan:ard TS by mie-1951 anc. that a license atercrent to imple- l a

entlast tne these TS forcfG3NS cuarter 1953.Unit 1, the lead A EARCG EWR-6 plant, is preparing would report a topical be reavested cucin$

for submitta in 1953, justifying the celetion of commitments to install post ac:ident neutron  !

flum monitors to meet Regulatory Guide 1.97 requiretents. The licensee is con- ,

sidering the purchase of the GGNS PRA study performed by Sandia Laboratory for l use in safety improvement studies.

Some plant pr:blem areas are shown en Sheets 20 and 21. The licensee said that instru? tnt and control surveillance tests are on the critical path for refueling l outages and t*at test schedules, procedures, and equipment are being evaluated (

to re:ute time from 60 days to 45 days. Another means being considered to '

shorten refueling outages is the use of a third cecay heat cooling system.

i 00eratiCPs, mairteFan:e an: te:haical support evaluaticns are snc.n er Sneets  !

22-26 of En:1:sure 2. Tre Oa:Lle; ef c,;tstard 4 ; aterial r:r::afor-aa:e i re: orts (MN Rs) has teen re:v:ed frem 546 at tne cegirning of 193C to less tran i 100 in Ce: emeer 1957. The nu.:er of design enange packages (OCPs) and design j Change reports (DCRs) has been recu:ed f ecm 1250 in January 1957 to 536 in Ce:e-ter 1957. C:05 aed D Rs ir:1ude b:th the nu: lear stes sup;1y system and balan:e of plant equipment.

Engineering and Quality program crgani:stiens and init,iatives are shown on Sheets 27-33 of Enclosure 4. A major thrust in achieving quality effectiveness is to emphasi:e quality control insten: of complian:e. The organi:ation for l ovality related programs has been changed from that shown on Sheet 32 to t, hat i she.in on Sheet 33. In the new ergani:ation, the in-line cuality :entrol fun:- l tions of inspe: tion and ceficiency control are se:arated frem the in:epencent l quality assurance fun:?, ions of audits, ebservations, and assessments. The con-figuention manage ent init,14tives (Sheets 28 and 29) will ed a -ajor effert l i

in 1955. l The completion of Unit 2 will be reassesses in 1959 to cetermine if the acci- i tional capa:ity would be ree:ed in the 1990s. In the interim, quality assur- l an:e anc maintenan:e pecgrams are in effe:t to preserve equipment, ano a.,so:iated i records. Tne unit is about 35'. : plete. l

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3 On December 2 and 3, the licensee conducted a general tour of the facility.

Incluced in the tour were the emergency operations facility, the simulator, the Unit 1 control room which was being enlarged to include offices for supervisors, and the Unit 2 containment. Also a video tape showing removal of a stuck fuel assembly was viewed.

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Lester I., Kintner Senior Project Manager Project Directorate II-I Divisien of Reactor Projects I/II See next page f~k a

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0:ht%fR LKintrer EAdensam d.D.;2^ W /5$

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Distribution See attached sheet

f Mr. Oliver D. Kingsley, Jr.

System Energy Resources, Inc. Grand Gulf Nuclear Station (GGh5)

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Mr. Ted H. Cloninger Mr. C. R. Hutchinson Vice President Nuclear Engintering GGNS General Manager and Suppert System Energy Resources, Inc.

Syttc:a knergy Resources, Inc. Post Office Box 756 Post Office Box 23054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39205 Robert B. McGahee, Esquire The Honorable William J. Guste, Jr.

Wise Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804 Nicholas S. Reynolds. Esquire Bishop Liben an, Cook, Purcell Office of the Governor and Reynolds State of Mississippi 1200 17th Street, N.W. Jackson, Mississippi 39201 Washington, D. C. 20036 General Mr. Ralph T. Lally Attornefuilding Gartin Manager of Quality Assurance Jackson, Mississippt 392C5 I Middle Scuth Utilities Syster

! Services, Inc.

! P.O. Box 61000 Mr. Jack McMillan Director j hew Orleans, Louisiana 70161 Division of Solid Wsste Management i Mississippi Departrent of Natural j Mr. John G. Cesare Resources Director, Nuclear Licensing System Energy Resources, Inc. Post Office Box 103E5 l P.O. Box 23054 Jackson, Mississippi 39209 I Jackson, Mississippi 39205 i Alton B. Cobb, M.D.

l Mr. R. W. Jackson, Project Engineer State Health Officer Bechtel Power Corporation State Board of Health 15740 Shady Grove Road P.O. Box 1700 Gaithersburg, Maryland 10877-1454 Jackson, Mississippt 39205 Mr. Ross C. Butcher President Senior Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Ccm ission Port Gibson, Mississippi 39150

, Route 2. Box 399

Port Gibson, Mississippi 39150

) Regional Administrator, Region !!

] U.S. huclear Regulatory Comission i 101 Marietta Street, N.W., Suite 2900 ,

! Atlanta, Georgia 30323  !

l

Mr. Jares E. Cross j GGNS Site Director (

j Systes Energy Resources, Inc. I P.O. Box 756 Port Gibson, Mississippi 39150

)

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ENCLOSURE 1 ATTENDEES NRC-SERI MEETING December 2, 1987 Juan Unda Spanish CSN John Mathis NRC, Resident Inspector Gus Lainas NRC, AD, Region II Reactors Elinor Adensam NRC, Director, PDII-I Ross Butcher NRC, Sr. Resident Inspector les Kintner NRC, Project Manager Oliver Kingsley SERI, V.P. Nuclear Operations Ted Cloninger SERI, V.P. Nuclear Engineering & Support Steve Feith SERI, Director Quality Programs Guy Cesare SERI, Director Licensing Jim Cross SERI. Site Director Randy Hutchinson SERI, GGNS General Manager Fred Titus SERI, Director Nuclear Plant Engineering Av.

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j ENCLOSURE 2 HANDOUT PREPARED BY ,

SYSTEMS ENERGY RESOURCES, INC.

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l PEETING AGENDA BRIEFING OF NRC NRR MANAG9ENT ESC CONFERENCE ROCN #1 2:30 P.M. ',

DECEMBER 2, 1987 I, INTRODUCTION

0. D. KINGSLEY, JR.

A. PURPOSE OF MEETING l B, SERI ORGANIZATICN

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II, t0 CLEAR OPERATIONS GOALS AND OBJECTIVES 0. D. KINGSLEY, JR. j t

III, GGNS SEPTEMEER 1%7 INPO AUDIT C R. HUTCHINSC6 I

IV. RF02 STATUS / SCHEDULE C, R. HUTCHINSC(1 V. LICENSING ACTIVITIES J. G. CESARE A, fDGRESS ON CLOSURE OF IN'T!AL L! CENSING CCitilTMENTS B. PRIORITv PF02 SUPPORT L flS i C, KEY 1988 ACT!v! TIES  !

VI, PLANT OPERATIONS, MAINTENANCE, AND TRAINING J. E. CROSS  ;

A, OPERATICris, PAINTENAfCE, AND  !

i TECHNICAL SUPPORT EVALUATIONS B. PLANT PROBLEM AREAS l C, CREW PERFORMANCE IMPPOVEMENTS I D. ftCR REDUCTICti VII. ENGitEERING/0VAllTY PROGP#G INITIATIVES T. CLONINGER/

i. TITUS F. W.

INTRODUCTION (THC)

A, CONFIGURATION MANAGEMENT INITIATIVES (FWT)

B, QUALITY PROGRAMS REORGANIZATION (THC)

C, GGNS UNIT 2 D. SITE MASTER PLAN VIII DISCUSSION /NRC OUESTIONS IX, CONCLUSitTS

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J14Ft'.187112404 - 2

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SYSTEM ENERGY RESOURCES 11/07/57 -

W. CAVANAUGH, til PRESIDENT &

CHIEF EXECUTIVE OFFICER I

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J. L. GLOUNT L. E. maf5tEK A. I GEERAL CouMsEL CORP. CDeusICATIONS I SI T I

I l I W. L. A80ERSON l

l NANAGER

! INTERNAL ALEITING l

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o. o. acINGSLEY. A. T. H. CLONINGER G. E. HAROER R. J. LA80Y vim PeESIDENT VICE WESIMNT I VICE PRESIDENT VICE PRESIDENT l

sesC. OPEa4TIONS Muc. ENG. C SUPPORT l ACCT. C TE ASUE R HUNW ES. E ADNIN.

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I I I I Ii l 1 J. E. CROSS J. S. ESAE F. W. TItuS T. E. K AVES, JR. S. M. FEITH D. R. DENTON D. A. RUETER J. J. FLENING M TE 01E CTOR DIECTOR DIRECTOR DIRECTOR DIECTOR DIECTOR DIRECTOR DIRECTOR GGNS . seELEAR LIENSING Muc. PLANT ENG. NUC. SUPPORT QUALITY PROGRANS ACCOLMTING CORP. SERVIE S MUNAss RESOURCES L

i R. C. FROM W. C. FINCH M. 8. ELLiff J. D. HARRINGTON G. A. ELLIS ACTING UNIT II ASSISTANT te4 NAGER 8Ws4GER EW REE C PK P N SS TE CONST. SUPT. TEASUER SUDGET C RATES ASSISTmT TO VIE PESIDDIT. ,

MUCLEA4 OPERATIONS

11/07/87 O. D. KlHCSIEY l

VICE PRESIDENT NUCtIAR OPERATIONS I

I J0 M . J.E. CROSS IMRECIDR SITE (EECTOR NUCtfAR UCDISWO 00NS I I M.L.CRAWFDRD 3. H. HOBBS R. C. FRON C. R. HUTCHINSON MANAGER MANACDt MANAGER CENERAL PtANT UCENSINC UCDfSMG SUPPORT MANAGER

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MANACDt SPECIAl. PR(WECTS R. W. MARTM K. E. BEATTY SITE TRAINHC CONTMOLLER SUPDt:NTDMNT I I A.S.MCCURDY J. P. DeWMETTE. JR. M. J. WRICifT J. C. ROINITIS MANAGER MM4AC;a MANAGER MANACIR

, PLANT OPERATIONS PLANT MAINTENANCE PLANT SUPPORT PLAlfr MOD. & CotGT.

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. o 11/07/87 T. H. CLOlllNCER VICE PRESEINT NUCLEAR ENGINEIRING & SUPPORI S. M. FUTH F.W.THUS T. E. REAVES. JR.

DutECIDR DfRECTINI DIRECTOR QUAUTY PROGRAMS NUC.PLhR. Dio. NUC1 EAR SUPPORT W. C. FINCH ACTING UNIT E S. F. TANNER MANAGDt CONSTRUCTION SUPT.

W. F. ADCOCK L R. MWY !

MANAGER QUAUTY SDMCE3 RAD. & DW. SDN.

J. E. IME3 C. W. ANGLE J. B. LEE MANAODt MANAGUt ACTING MANAGER QuAUTY SYSTEMS OPERATIONAL ANAL NUCtfAR FUELS

' D. L PACE 'i H. D. MORGAN MANAGER MANAGER NUCLEAR DESIGN CONT. & SFI. SVCS

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NUCLEAR OPERATIONS - MANAGEMENT BY OBJECTIVES 1988 G0ALS 8 OBJECTIVES I

APPROACH O ACHIEVE EXCELLENCE IN NUCLEAR PLANT OPERATIONS - BEST UNIT O SUPPOPT MSU SYSTEM BY SERVING AS MODEL IN IMPROVING t PERFORMANCE i

O CONTINUE EMPHASIS ON IMPROVING basic GGNS OPERATIONAL AREAS OF TRAINING, OPERATIONS, CHEMISTRY, RADIATION i a PROTECTION, MAINTENANCE, OUTAGE MANAGEMENT, EMERGENCY PREPAREDNESS, AND HUMAN PERFORMANCE USING INP0 CRITERIA AS STANDARDS .

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0 ESTABLISH IMPROVED PERFORMANCE STANDARD OVER SEVEPAL

YEAR PLANNING PERIOD 0 GOALS ESTABLISHED FROM GGNS PLANT PERFORMANCE INDICATORS AND VARIOUS EVALUATIONS O PERFORMANCE STANDARDS BASED ON EVALUATION OF INP0 PERFORMANCE DATA i 0 SALP, INSPECTION REPORTS, ROUTINE INTERFACE WITH NRC .

PROJECT MANAGER AND RESIDENT INSPECTOR FACTORED INTO l GOALS j 0 OTHER GOALS ESTABLISHED TO FOCUS ON SPECIAL IMPROVEMENT l AREAS j I OVERVIEW 0 PLANT PERFORMANCE INDICATOR BASED l

0 SPECIAL IMPROVEMENT AREAS i  !

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t J12 MISC 87113001 - 3 l

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I KEY PLANT PERFORMANCE INDICATOR RELATED GOALS i

YEAR TO 1987 INDUSTRY 1988 ,

INDICATOR DATE GOAL AVG GOAL i (10/31/87)  ;

1. EQUIVALENT 91.53 >75 60.3 >85  !

AVAILABILITY l i

2. FORCEO OUTAGE 2.21 <9 17.7 <6 RATE

3. SCRAMS 2 14 3. 9 13 l

4. SAFETY SYSTEM 0.33 11 1.2 11 s ACTUATIONS ,

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(per safety system) i

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5. SAFETY SYSTEM Requirements Being Evaluated by INPO  ;

UNAVAILABILITY

6. RADIATION DOSE 88.3 <425 622 <160 f j; (Man-Rem) (BWR)

7. GROSS HEAT RATE 10724 <10850 10315 <10700 I (BTU /KWH)  ;

8. LOST TIME ACCIDENT 0.23 <0.4 0.4 <0.3  ;

i RATE j

(#/200,000 MH) i

9. RA0 WASTE 316.9 <566 493 <600  !

GENERATION (BWR) l

(cubic meters) (

t f 10. FUEL RELIABILITY .000081 <.003 .0032 <.003  ;

! (uCi/gm) (BWR)  ;

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O SPECIAL IMPROVEMENT AREA GOALS PROGRAM OR PROCESS IMPROVEMENT

1. DESIGN CHANGE IMPLEMENTATION PROCESS /TECHN!0UE

2. INTEGRATED LIVING SCHEDULE IMPLEMENTATION

3. PLANT DEFICIENCY REPORTING SYSTEMS j CONSOLIDATION, PROCEDURE DEVELOPMENT, AND IMPLEMENTATION

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4. SURVE!LLANCE TESTING PROCESS AND PROCEDURE l

' IMPROVEMENTS l

5. OUTAGE PLANil!NG AND EXECUTION IMPROVEMENT ORGANIZATIONAL EFFICIENCY

1. MODIFICATION AND CONSTRUCTION CONTRACT PERSONNEL EFFICIENCY

2. MAINTENANCE IMPROVEMENT PLAN IMPLEMENTATION

3. TECHNICAL SUPPORT GROUP REORGAN!ZATION

4. SHIFT OPERATIONS CREW ENHANCEMENTS l 1

TRAINING /0PERATOR LICENSING l 1. LICENSED OPERATOR PROFESSIONALISM

2. SECOND ROUND ACCREDITATION SELF EVALUATION l

REPORTS

3. S!MULATOR CERTIFICATION PLAN 1

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4. TRAIN!NG STAFF OPERATIONS EXPERIENCE IMPROVEMENTS OTHER SPECIFIC AREAS

1. CONTINUE EMPHASIS TO IMPROVE POSITIVE SALP TRENDS

2. 1987 INP0 PLANT EVALUATION FINDINGS CLOSE0VT AND CONTINUED EMPHASIS TO ACHIEVE HIGHEST RATING

3. SIMS DEVELOPMENT AND IMPLEMENTATION

4. TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM J12 MISC 87113001 - 4 7

. INP0 NOTES

SUMMARY

S/U ASSIST INP0 INP0 VISIT EVALUATION EVALUATION 1984 1986 1987- l FINDINGS 64 23 11  :

4 5 GOOD PRACTICES i

1987 INP0 EVALUATION PURPOSE AND SCOPE j

INP0 CONDUCTED AN EVALUATION OF SITE ACTIVITIES TO MAKE AN OVERALL DETERMINATION OF PLANT SAFETY, TO EVALUATE l MANAGEMENT SYSTEMS AND CONTROLS, AND TO IDENTIFY AREAS

NEEDING IMPROVEMENT, INFORMATION WAS ASSEMBLED FROM DISCUSSION, INTERVIEWS, OBSERVATIONS, AND REVIEWS OF ,

DOCUMENTATION, t

THE INPO EVALUATION TEAM EXAMINED STATION ORGANIZATION AND 4

ADMINISTRATION, OPERATIONS, TECHNICAL SUPPORT, TPAINING AND OVALIFICATION, RADIOLOGICAL PROTECTION, CHEMISTRY, EMERGENCY PREPAREDNESS, AND OPERATING EXPERIENCE REVIEW, THE TEAM ALSO OBSERVED THE ACTUAL PERFORMANCE OF SELECTED EVOLUTIONS  !

INCLUDING SURVEILLANCE TESTING. AS A BASIS FOR THE EVALVATION, INPO USED ITS april 1987 PERFORMANCE OBJECTIVES i

! AND CRITERIA FOR OPERATING AND NEAR-TERM OPERATING LICENSE i l PLANTS THESE WERE APPLIED AND EVALUATED IN LIGHT OF THE l 1 EXPERIENCE OF TEAM MEMBERS, INP0'S OBSERVATIONS, AND GOOD

PRACTICES WF. THIN THE INDUSTRY.

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! INP0'S G0AL IS TO ASSIST MEMBER UTILITIES IN ACHIEVING THE l

) HIGHEST STANDAPDS OF EXCELLENCE IN NUCLEAR PLANT l l OPERATION, THE RECOPEENDATIONS IN EACH AREA ARE BASED ON

! BEST PhACTICES, RATHER THAN MINIMUM ACCEPTABLE STANDARDS OR j REQUIREMENTS, ACCORDINGLY, AREAS WHERE IMPROVEMENTS ARE RECOMMENDED ARE NOT NECESSAR!LY INDICATIVE OF UNSATISFACTORY PERFORMANCE, PCOM RF02 SLIDE SHOW1 - 1 7

BENEFICIAL PRACTICES AND ACCOMPLISHMENTS NOTED o THE OPENNESS AND RECEPTIVENESS OF THE MANAGEMENT-TEAM TO NEW IDEAS, THEIR AGGRESSIVENESS IN PURSUING IDENTIFIED PROLLEMS AND THEIR EXTENSIVE INVOLVEMENT IN DAILY PLANT ACTIVITIES, l l

o THE PERFORMANCE RECORD ACHIEVED DURING THE PAST YEAR AS REFLECTED BY RECENT TRENDS IN KEY PERFORMANCE INDICATORS.

o THE COMPREHENSIVE LONG TERM PLANS IN PLACE T0 IMPROVE THE EFFECTIVENESS OF VARIOUS PROGRAMS AND FACILITIES, EXAMPLES INCLUDE THE MAINTENANCE IMPROVEMENT PLAN AND THE SITE MASTER PLAN, 1

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e OVERALL 1987 RESULTS CATEGORY 2 OVERALL PERFORMANCE IS EXEMPLARY, INDUSTRY STANDARDS OF EXCELLENCE ARE MET IN MANY AREAS, NO SIGNIFICANT WEAKNESS NOTED, f

PCOM RF02 SLIDE SHOW1 - 3

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t 1987 INPO FINDINGS

SUMMARY

. t o CONTRACTOR' ADHERENCE TO SEVERAL ASPECTS OF THE STATION INDUSTRIAL SAFETY PROGRAM NEED IMPROVEMENT l

, o SOME STATION EQUIPMENT IS NOT READILY ACCESSIBLE FOR  ;

l OPERATION AND MONITORING o STATION ENGINEERING ACTIVITIES ARE NOT COORDINATED TO  ;

i ACHIEVE MAXIMUM EFFICIENCY AND EFFECTIVENESS,  ;

i i o ADDITIONAL ATTENTION NEEDS TO BE FOCUSED ON I IMPLEMENTING DESIGN CHANGES NECESSARY TO MAKE TEMPORARY  !

) ALTERATIONS PERMANENT, l

l l 0 SIMULATOR SCENARIOS SHOULD BE IMPROVED TO ENSURE THAT i

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ALL LEARNING OBJECTIVES ARE ACCOMPLISHED AND THAT USE  !

0F SIMULATOR TIME IS EFFECTIVE, l

) o SOME ADMINISTRATIVE ASPECTS OF THE RADIATION

] PROTECTION PROGRAM NEED IMPROVEMENT,  !

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o IMPROVEMENTS ARE NEEDED IN SOME RADIOLOGICAL l CONTAMINATION CONTROL PRACTICES,  !

i o SEVERAL LONGSTANDING CHEMISTRY PROBLEMS INVOLVING j 4

!N-LINE MONITORS HAVE NOT BEEN RESOLVED, i o IMPROPER MONITORING AND CONTROL OF MAKEUP WATER i DEMINERALIZERS CONTRIBUTE TO PRODUCTION OF LESS THAN l OPTIMUM OUALITY WATER, l l l

0 CHEMISTRY LABORATORY CONTROL PRACTICES NEED IMPROVEMENT f l; i

) o INVESTIGATIONS / ANALYSIS OF IN-HOUSE OPERATING EVENTS l 1 INVOLVING PERSONNEL ERRORS ARE NOT IDENTIFYING AND l l DOCUMENTING CONTRIBUTING FACTORS, i l I 3

PCOM RF02 SLIDE SHOW1 - 4 l l' l

RF02 MAJOR WORK TURBINE o DISASSEMBLY / INSPECTION OF LOW PRESSURE TURBINE.

o ROTOR DISC UT INSPECTION REFUEL o FUEL SHUFFLE o REACTOR VESSEL INTERNAL ISI o REMOVAL OF VIBRATION INSTRUMENTATION DIESEL GENERATORS o TDI OWNER'S GROUP MAINTENANCE:

DIV II COMPLETE DIV I NOT COMMENCED o DIV III MAINTENANCE COMPLETE o ECCS TESTING:

DIV III DIV II SSW BASIN o CHEMICAL CLEANING SSW A BASIN AND LOOP o FLOW BALANCE:

"B" LOOP "A" LOOP TO BE PERFORMED AFTER CLEANING COMPLETE PCOM RF02 SLIDE SHOW1 - 5 l 2,

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i CONDENSB i ,

o CHEMICAL CLEANING 0F CIRCULATING WATER  ;

l o ON-LINE TUBE CLEANING SYSTEM INSTALLATION l PLANT EFFICIENCY IMPROVEMENTS_

l 0 INSPECTION AND REPAIR OF ALL HEATER AND MSR DUMP VALVES l

) o CONDENSER CLEANING  ;

} o INTERNAL CONDENSER WORK j o INSTALLATION OF TUBE CLEANING SYSTEM  :

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j RF02  :

MAJOR DESIGN WORK 1 i  !

l REGULATORY WORK ITEMS i o ATWS 10CFR50.62 (SLC) l o POST ACCIDENT MONITORING (REG GUIDE 1.97) l o DETAILED CONTROL ROOM DESIGN REVIEW WORK  !

o FIRE PROTECTION UPGRADES (APP, "R")  !

I o DROR INSPECTIONS ON DIESEL GENERATORS I

l o TURBINE ROTOR DISC INSPECTIONS j o VISUAL RADIATION ALARMS IN HIGH NOISE AREAS l l 0 TIME DELAY TOPAZ INVERTER LOGIC

o CIRC WATER WORK ,

j o ANS S!REN SYSTEM UPGRADE j i o ROSEMOUNT TRANSMITTER REPLACEMENT AND OTHER E/0 ITEMS l 0 HEAT DETECTOR /SM0KE DETECTOR REWORK ]

j o RWCU ISOLATION VALVES  ;

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ACTIONS TAKEN TO MINIMIZE POTENTIAL  ;

FOR DRAINING THE VESSEL i

o IMPLEMENT INTERLOCKS ON RHR S/D COOLING AND LPCI SUCTION VALVES. l o MINIMIZING THE TIME THAT 2 RHR S/D COOLING LOOPS ARE i INOPERABLE l

i j o ONE (1) ECCS SYSTEM IS FUNCTIONAL AT ALL TIMES i

o ALTERNATE COOLING METHODS ARE DEMONSTRATED AS CAPABLE j l OF REMOVING DECAY HEAT PRIOR TO BEING DECLARED AS AN l 1 ALTERNATE MODE.  ;

l' o A STATUS BOARD IS PROVIDED IN THE CONTROL ROOM WHICH ,

CLEARLY INDICATES THE OPERABLE ECCS SYSTEMS, THE l l SHUTDOWN COOLING MODE BEING UTILIZED AND THE STATUS OF l j ALL SYSTEMS WHICH COULD CAUSE INADVERTENT VESSEL l i

i DRAINING.

I o SPECIAL CONTROLS ESTABLISHED TO REQUIRE THE REFUELING FLOOR COORDINATOR AND THE SHIFT SUPERINTENDENT TO L

! i APPROVE MANIPULATION OF ALL VALVES WHICH COULD DRAIN

THE VESSEL WHILE THE VESSEL HEAD IS DETENSIONED.  ;

l o TRAINING PROVIDED TO ALL OPERATIONS SHIFTS AND  ;

l REFUELING FLOOR COORDINATOR DISCUSSING THE TIME TO  !

j DRAIN THE VESSEL, POTENTIAL CONSE0VENCES, l l RESPONSIBILITIES FOR APPROVAL OF VALVE MANIPULATIONS  :

I WHICH COULD CAUSE INADVERTENT DRAINING, AND l l CONTINGENCY PLANNING. l I i I i

1 i

l l 1  !

l PCOM RF02 SLIDE SHOW1 - 7 l l Iy l

CONTINGENCIES FOR EVACUATION AND CLOSURE OF CONTAINMENT o TEMPORARY CONTAINMENT HATCH WHICH COULD BE SET IN LESS THAN FIVE (5) MINUTES TO MINIM 1ZE AIR FLOW FROM CONTAINMENT TO AUXILIARY BUILDING.

o CONTAINMENT AIR LOCK DOORS MAINTAINED IN A CONDITION WHERE AT LEAST ONE DOOR CAN BE MANUALLY CLOSED.

o PLAN IN PLACE FOR CONTAINMENT CLOSURE IF IT BECOMES NECESSARY.

i 4

PCOM RF02 SLIDE SHOWI - 8 .

y,

f BRIEFING OF NRR MANAGEMENT DECEMBER 2, 1987 LICENSING ACTIVITIES o PROGRESS TOWARD CLOSURE OF INITIAL LICENSING COMlilTMENTS o PPIORITY RF02 SUPPORT ACTIONS o KEY 1988 ACTIVITIES l

4 j

l J12 MISC 87113002 - 1 lb f l

PROGRESS TOWARD CLOSURE OF INITIAL LICENSING COMMITMENTS OVERVIEW 0F FULL POWER OPERATING LICENSE CONDITION ITEMS o 20 OLC ITEMS REQUIRING MODIFICATIONS o 25 OLC ITEMS REQUIRING OTHER RESOLUTION o 41 OUT OF 45 OLC ITEMS COMPLETED BY RF01 KEY NRC WORK ITEMS o COMPLETED BY RF01

1. S0ll STRUCTURE INTERACTION (OLC 2.C.(6))

2. PRESSURE INTERLOCKS ON VALVES INTERFACING AT LOW AND HIGH PRESSURE (0LC 2.C.(18))

3. STANDBY SERVICE WATER SYSTEM (OLC 2.C.(20))

4. SPENT FUEL POOL VENTILATION SYSTEM (OLC 2.C.(21))

5. REMOTE SHUTDOWN PANEL (OLC 2.C.(22))

6. RELIABILITY OF DIESEL GENERATORS (0LC 2.C.(25)(A))

7. NUREG-0737 MODIFICATION OF ADS LOGIC (OLC 2.C.(33)(F))

o SCHEDULED FOR RF02

1. CONTAINMENT PURGE (0LC 2.C.(16))

2. LOW PRESSURE TilRBINE INSPECTION (0LC 2.C(26) -- 1 oF 3)

3. ATWS SLCS ALTERNATE ROD INSERTION l

4. DCRDR (OLC 2.C(36))

5. PEACTOR WATER LEVEL TRANSMITTERS

6. SSW FLOW BALANCE AND INSPECTION o OUTSTANDING / FUTURE OUTAGES

1. NEUTRON MONITORING SYSTEM

2. IMPROVED SPENT FUEL POOL DECAY HEAT REMOVAL CAPABILITY J12 MISC 87120102 - 1 17

PRIORITY RFO? SUPPORT ACTIONS o TOTAL NUMBER OF TS/0L ITEMS AWAITING NRC RESPONSE ACTION: 10 o HIGH PRIORITY ITEMS 3.0.4 TS EXCEPTION / SUBMITTED 11/19/87 /

NEED BY 12/7/87 i RWCU TS CHANGE 8 EXEMPTION / SUBMITTED 11/24/87 /

NEED BY 1/3/88 ATWS TS CHANGES / SUBMITTED 11/24/87 0 0THEP !TEMS REQUIRED TO SUPPORT RF02 RELOAD LICENSING PACKAGE - CYCLE 3 FIRE PROTECTION - ADDED FIRE DETECTION INSTRUMENTATION RCIC/RHR HIGH STEAM FLOW R.G. 1.97 FLUX MONITORING DEFERRAL ISI RELIEF RE0 VEST (RPV N022LES)

ISI RELIEF REQUEST (ASME CODE ADDITION FOR CLASS 1 COMPONENTS)

ISI RELIEF REQUEST (ASPE CODE ADDITION FOR CLASS 3 COMPONENTS) l J12 MISC 87113002 - 2 II

i-  :

t l

l

SERI LICENSING - KEY 1988 ACTIVITIES j L

l 0 TECHNICAL SPECIFICATIONS l 1. BWROG TS IMPROVEMENT PROGRAM (REFORMATTING PER COMMISSIONER POLICY STATEMENT) j i

2. FIRE PROTECTION, NRC GENERIC LETTER 86-10 ).

EMERGENCY DIESEL, RELIABILITY / TESTING IMPROVEMENTS I l 3.

! 4. APPLICATION OF TS 3.0.4, NRC GENERIC LETTER 87-09 f 1 i

5. BWROG RPS INSTRUMENTATION, IMPROVEMENTS TO SURVEILLANCE i i INTERVAL AND A0T l

. o PROGRAM / PROCESS IMPROVEMENTS l I 1, 10CFR50.59 PROCESS ASSESSPENT AND IMPROVEMENTS (SUPPORT e TECH SPEC IMPROVEMENT PLAN)  !

i 2. COORDINATION OF CONSOLIDATION OF PLANT DEFICIENCY -

l IDENTIFICATION AND EVALUATION PROCESS  !

i o OTHER

1. REG. GUIDE 1.97 NEUTRON MONITORING SYSTEM f

2. NUREG 1150/GGNS PRA RELATED ACTIVITIES j lI 9

3. HYDROGEN CONTROL PROGRAM WPAPUP l l

l 4 IMPLEMENTATION OF IMPROVED CLASS A DOSE MODEL l 4

l 4

i i

i  !

l

-l J12 MISC 87120102 - 2 If  !

i

PLANT PROBLEM AREAS I. LOSS OF THERf'AL EFFICIEfGY C0f0ENSER CLEAtlL!?!ESS EXCESS HEATLOAD LOW PRESSURE HEATER OPEPATIOff 2

II. FREQUEtri FAILURE OF 0FFGAS H AtlALYZER CELLS EXCE'SGIVEFO!STURE LEfGTHLY REPLACEffflT PROCEDURE DESIGil CHAtlGE IMPLEMEPFED FIRST WEEK OF ibvEFSER Illi PAlti STEAM Lif>E PADIAtiUll'OtUTOR DRIFT IDENT!FIED Ifl 1987 AS PROBLEM IPEREASESURVE!LLAll?EIff7ERVAL-1/2ISOLAT!0fl PURCHASE NEW Foil! TORS - PF02 IV, fMCU LEAVAGE BOLTED HEAT EXCHNJGER HEAD FLAfJGF LEAX REOCCURRED 4 T!MES - 5.6 FAN-Pat MJST KEEP SEALED TO PREVEffT C0flTAlfffffT BECOMlfG AIRPr@NE REDESIGt1ED SEAttfG SURFACES - RF02 V. IflSTRUMEf(T AfD Cot 1 TROL SECTION SURVEILLNCES

• CURRENT SURVEILLNCE PROGR#1 REQUIRES APPROX!P'ATELY 60 DAYS, EXTEftslVE EVALUATIOfl WILL BE f4ECESSARY TO SUPPORT A 45-DAY REFUEL!fG OUTAGE GOAL.

BETTER SCHEDutifG, PROCEDUPE RESTRUCTURIfG. #O f;EW EQUIPMENT VI. SPURIOUS ACTUATI0fl 0F LO-LO SET RELIEF VALVES OCT0BER 4TH SPURIOUS ACTUATICW OF 2 LO-LO SET VALVES.

fD CAUSE COULD BE DETEPf11NED.

FORE!Gr4 BWR-6S Cot.TACTED AND If4DICATED THEY KAD EXPERIENCED SIMILAR PROBLEMS. j DES!GN CHANGE - RF02 TO IffROVE GRCUt0!?G MO REDUCE DF 1 JO911SC87120101 SUSCEPTAR!LITY.

M !

I

.. . . . = - .. . . _ _ _ _ _ -- . . ~ _ . __ . .- . .- _ _ _

i .

3 ,

• i I

a Vll. SERYlCE LIFE OF AGASTAT PELAYS ORIG!fML SERVICE LIFE OF AGASTATS PECdlRED APPROX!PATELY i 300 TO BE REPLACED EACH REFUELifG OUTAGE. i

REPLACEMEtlT

EXTENSIVE MANHOURS A10 PLANN!flG

INCREASED EXPOSURE TO IfMDVERTEin OPERAT!0fl  !

INCREASED TEST!?G l

INCREASED CHAtCE OF CABLE TERMINAT10tl ERRORS  ;

l INCREASED CHAtlCE OF EARLY IN RELAY LIFE FAILURE i ESTABLISH A QUALIFIED LIFET!ME TEST WHICH SittJLATES ACTUAL  !

l PLANT C0fDITIONS. l 4 i i'

TEST!tG SHOWED SPECIFIC OUALIFIED LIFET!ME IS GREATER THAt1 GENERIC SPECIFICAT!0tlS INDICATED.  !

! l l '/II( DEGRADAT!0tl 0F PLAtlT SERVICE WATER WELLS WELL CAPABILITIES DECREAS!tG WITH TIME Ifl SERVICE.

l I j LATERAL DEPOSIT!0fl f l WELL FIELD DETERIORATI0tl i PUMP DETERIORAT!0fl CAISSOff SAtO BUILDUP C0tPREHEtislVE WELL MANAGEMENT PROGR#1 DEVELOPMEtR ,

f 4

PERIODIC WELL REDEVELOPtfMT PERIODIC E0V!Ptff4 SERVICitG j PERIODIC SNPLifG PROGR#i NO FLCH NONITORitG i IX. IN 1988 A CHEMICAL IFPROVEfftIT PRCGR#i WILL BE DEVELOPED TO ADDPESS PROGRAF.S, PERFORMAtlCE, #O EQUIPfft#.

EQUIPfftG PGT RELIABLE l MAINTEtMNCE N O ?%tMGEM NT INVOLVE M NT PROCEDURES EVALUATI0tt CHEMISTRY If0!CATORS WILL BE ESTABLISHED.

X. STNCBY L10VID CONTROL SYSTEM ADDRESSED BY NUCLEAR PLArn EfGINEERifG ,

. JO911SC87]20101 7./

I

OPERATIOflS, PAltlTEtWlCE, no TECHillCAL SUPPORT EVALUATIOflS OBJECTIVES:

Ftro PPOBLEtG EARLY AtO INITIATE IMPROVEtENT - DON'T EE SATISFIED IMPOPTAtlT TO LOOK AT OURSELVES Irl A CRITICAL t%fJtlER TO IMPRO'E PERFORt%NCE.

MANAGEMEtiT IfNOLVED IN ALL EVALUATIONS.

INDUSTRY EXPERTS WITH BOTH UTILITY N1D MILITARY NUCLEAR EXPERIEtJCE UTILIZED.

REVIEWED PERFOPFNJCE DATA, REVIEWED PROCEDURES, IriTERVIEWED PERSONflEL, Af D OBSERVED Iff-PLAT 4T PERFORtWJCE.

RESULTS:

OPERATInf;S EVALUATI0tl C0tJTROL Ptm CONDUCT CONTROL R0cra Ccnwo FUticT!an C0tRROL P m ' REDESIGN F#lAGEMEtIT IfNOLVEMENT Ifl TFE PLNIT CLEAR SFT OF STAtOAPSS FAltITEfWJCE EVALUATION PLAtaltflG MO SCHEDULIPG CRAFT SUPERVISORS It1 THE FIELD STREtJGWEtlCOORDINATIONtEET!NG MoRE FORf%L! ZED fW t%1NTEfWlCE NO TEST!?G TECH SUPPORT EVALUATICWS ESTABL!$H A SYSTEM EtGINEERS PROGRAM

• FY RESPONSIBILITY BEWEEN MAINTEtWJCE, fE CLAR:

N O "ECHNICAL SUPPORT.

EVALUATION IS C0flT!NUlfG.

J09 MISC 87120101 p

CREW PERF0Pf%f!CE IffROVEfErITS OBJECTIVES:

CoflSISTEffT PERFORP#lCE FRCri ALL SHIFTS.

C0f1SISTEtlT STNOARDS.

CONSISTENT C0fi%f0 C0ffTROL.

CONS!STEf(T IPPLEf1EffTATIOfJ.

Mlfi!Ml7E C0fiTROL ROOM TRAFFIC.

M!fl!MIZE C0ffTROL ROCri fo!SE LEVELS.

ACTIOf t:

ISSUED PN!AGEMENT STAfCARDS.

TPAINED OPERATIONS #iD PNIAGEPENT.

TRAINED TRAINING STAFF.

SENIOR PN!AGEMEffT IfiVOLVEfENT TO ENSURE C0ftSISTEf1CY.

STNCARDS CLEARLY STATED - TRAINING NO TEST!flG CRITERIA CCftSISTEflT WITH STANDARDS.

GPAD!flG ST4 0ARDS WELL DEFINED TRAlfl!NG PP0 CESS IS f0NITORED BY PNlAGEMENT.

EfiSURE STAfCARDS ARE fMlf(TAlf!ED.

ENSUPE EVALUATIONS ARE CONSISTEflTLY GRADED AfD PEET '

F#tAGEPENT'S ST40ARDS OF EXCELLEfiCE.

PROVIDE IflSTANT FEEDBACK BOTH TO OPEPATICils no TRAINING ON THEIR PERFORPRCE.

f0fitTOR PERFOPFRJCE Ifl THE FIELD.

i 0 4- p

1987 WCR CLOSE00T PROGRAM COALS:

o LESS THAN 100 WCRS OVER OE WAR OLD AT THE END OF RF02 (NRC COMITENT).

o LESS THAN 50 WCRS OVER OfE WAR OLD AT TE END OF RFO' (CmPAth' G0AL).

SCOPE:

ON TE BASE DATE OF 12 JANUARY 1987, 548 MCPS WEPE OP91 milch WOULD EXCEED ONE WAR OF AGE ON 31 DECENER 1987, ACTIOfiS TO DATE:

THE ttCR DATA BASE HAS EEEN MODIFIED T0 INCLUDE AN ESTIMATED MJCR CLOSUPE DATE FOR EACH WCR, TFIS DATA SERWS AS THE ECHAllISM FOR TE ELEVATION OF PROELEM WCRS TO PANAG90!T, WED1Y EETINGS ARE ELD TO IDOUlFY SFECIFIC PROBLEMS Wi!CH IMilBIT TE CLOSURE OF fHCRS. fEW ftCRS APE ALSO DISCUSSED TO PREW THEM FRm BECCrilNG PART OF A FUTUPE BACKLOG MEPS IDENTIFIED AS POWIAL OPERABILITY CONCERNS ARE DISCUSSED AT TE PLAf6 MDPfl!NG f5ITING TO DISUPE PROPER AND TIELY MANACOUR ATTD RICti TO THESE ITEMS, JO911SC87120102 4y

THE CURPS(T STATUS OF THE F?iCR REDUCTION PROGPWi IS SFOdi BELOW:

o FfiCRS WUPKlfG ful:

WORK IN PROGRESS (f01-OllTAGE) 13 WOFK IN DROGPESS (CUTAGE) 37 EVALUATION Ifi PROGRESS 4 DRAWifG CHANGE CflLY .J_

SUBTOTAL 61 o F74CRS C(i HOLD (BYPL 1988 8 LATER): 27 TOTAL OPDi FT!CRS ff_

JCrailSC87120102 yf i

1 l

[

! DCP/DCR PEDUCTION PROGRAM i

G0AL:

l

LESS THAN 500 DCRS AND DCPS OWR TWO EARS OLD BY TE END OF 1987, j l'  !

t i

i SCOPE: j t

J I ON TK BASE DATE OF 1 JAf,UARY 1987, 1250 DCRS AND DCPS WERE OPEN

, l j THAT WOULD EXCEED Th0 EARS OLD ON 31 DECEFFI.R 1987,  !

l l ACTIONS TO DATE j i- ,.

THE CURRENT STATUS OF THE DCR/DCP PEDUCTION PROGRAM iS PROVIDED l EELCW:

)

i

! DCR/DCP CLOSURE St & ARY l

! BASE (3/2/87) 1250 .

t l l CLOSED / CANCELLED TO DATE -714  !

TOTAL PfrAINING OPEN 536  !

f t l l

j STATUS OF OPEN DCRS AND T4PS ItTtENNTAT!ON PECOMNDED 317 l

BALANCE TO BE CLOSED / CANCELLED 2219 l

t  :

TOTAL REN!NING OPEN 536 l

!i l

i l-

! t 1 '

J09 MISC 87120102 g

q ,;

a g 7 'T *

<V ~

ENGINEERING / GUALITY PROGRAMS INITIATIVES t x CONTINUE CONFIGURATION MANAGEMENT / DESIGN BASIS INITIATI"ES

• CONTINUE IMPA0VEMENT OF OPERATING EXPERIENCE IN ENGINEERING STAFF

• IMPROVE EFFECTIVENESS OF ISEG FUNCTION

• CONTINUE SHIFT OF QUALITY ORGANIZATION FROM COMPLIANCE BASED TO EFFECTIVENESS BASED

• CONTINUE PERFORMANCE OF SAFETY SYSTEM FUNCTIONAL INSPECTIONS

• AGGRESSIVELY IDENTIFY AND SUPPORT RESOLUTION OF PLANT DESIGN, OPERATION AND MAINTENANCE PROBLEMS M ~ CONTINUE IMPROVEMENT OF TECHNICAL SUPPORT OF LICENSING ISSUES AND SUBMITTALS

• REFLECT ABOVE IN NUCLEAR ENGINEERING AND SUPPORT GOALS AND OBJECTIVES

-J

PAGE 1 0F 2 CONFIGURATION MANAGEPENT INITIATIVES AS-BUILT PROGRAM 1986: MAJ0P PROGRAM IMPROVEMENTS MADE INCLUDING CAD SYSTEM POST RF01 PROGRAM ASSESSMENT CORRECTIVE ACTIONS OVER 90% COMPLETE (ECD 12/31/87) 1988 ACTIONS:

COMPLETE THE TURNOVER OF BECHTEL/GE DRAWINGS (150,000 DOCUMENTS)

COMPLETE THE WOPK-0FF OF LOWER TIER BACKLOG DEVELOP INTEGRATED CONFIGURATION CONTROL DATABASE SYSTEP DESIGN BASIS SYSTEM DESIGN CRITERIA (39 SYSTEMS)

OTHEP GENERAL CRITERIA / GUIDES 1

DESIGN BASIS CALCULATIONS CALCULATION TUoNOvER TO SERI (15,0C0 CAI.CULATIONS)

SERI REV!EW/ ACCEPTANCE OF CALCULATIONS INSTRUMENT SETPOINT/ CONTROL UPGRADED COMPONENT 0-LIST (27,000 ITEMS)

INSTRUMENT SAFETY FUNCTION BASIS DOCUMENTATION UPGRADED LOOP / LOGIC DIAGRAMS FOR 30 SAFETY RELATED SYSTEMS (200 LOOPS /540 LOGICS)

PERFORM UPGRADED INSTPUMENT SETPOINT CALCULATIONS TO REFLECT "INSTRUMENT SETPOINT METHODOLOGY" SE!SMIC QUALIFICATION FILES CONSOLIDATE SEISMIC QUALIFICATION FILES (382 PACKAGES)

ENvlRONMENTAL QUALIFICATION FILES i l

' l E0 SAFE SHUTDOWN LOGICS AND EcVIPMENT EVENT MATRIX REFORMAT, CONSOLIDATE EQ FILES (71 PACKAGES) l l

NRC MEETING - 1 gf

PAGE 2 OF ?

CONFIGURATION MANAGEMENT INITIATIVES FIRE PROTECTION APPENDIX R SAFE SHUTDOWN DIAGRAMS AND FIRE AREA LISTING RACEWAY As-BUILT VERIFICATION ELECTRICAL LOAD FLOW PROGRAM PROGRAM FOR: LOAD TABULATION AND CONTROL, VOLTAGE DROP,

RELAY /BREAKEP COORDINATION, LOAD FLOW /SHORT CIRCUIT, POWER CABLE DERATING SIMS

EXTENSIVE COMPONENT DATA BASE FOR MWO, PLANNING t

l CABLE INFORMATION SYSTEM TAKE0VER BECHTEL ELECTRICAL RACEWAY ROUTING PROGRAM

• FIRE WRAP CONFIGURATION, i IMPLEMENT ENHANCEMENTS:

VOLTAGE DROP CALCULAi10NS, SAFE SHUTDOWN IDENTIFICATION l I

1 i

s d

(

I.

i NRC MEETING - 2 LT

STANDBY LIQUID CONTROL SYSTEM (SLCS) MODIFICATIONS RF02 SYSTEM MODIFICATIONS ATWS SURVEILLANCE TEST PROBLEM SURVEILLANCE TEST PROBLEM RELIEF VALVE LIFTS DURING SURVEILLANCE TESTING CONTRIBUTING CAUSES l POSITIVE DISPLACEMENT PRESSURE C'lKING

, SMALL MARGIN TO RELIEF VALVE SETPOINT POOR TERT LOOP CONFIGURATION RESOLUTION ,

ADL PULSATION DAMPENERS RAISE DESIGN PRESSUPE TO 1500 PSIG '

RA!SE RELIEF VALVE SETPOINT IMPROVE TEST LOOP CONFIGURATION l

! l i l a

I '

l i

I l

l i

f 1 NRC MEETING - 3 3e

VICE PRESIDENT NUCLEAR ENGINEERING S SUPPORT I

DIRECTOR DIRECTOR DIRECTOR STAFF ENGINEER NUCLEAR PLANT ENGINEERING NUCLEAR SUPPORT GUALITY PROGRAMS MANAGER MANAGER MANAGER NUCLEAR DESIGN CONTRACTS S QUALITY SYSTEMS SUPPORT SERVICES MANAGER MANAGER MANAGER 0PERATIONAL ANALYSIS l RAD G ENVR SVCS QUALITY SERVICES I

MANAGER ENGItJEERING SUPPORT .

____z___________

. _ _ . _ _ . . . . , _ . , _ _ _ _ _ _ _ _ _ . = . _ , - _ _ . . . _ . ., . _ _ , _ _ , _ _ _ . _ . _ _

DIRECTOR QUALITY ASSURANCE b

MANAGER MANAGER _ MANAGER PROGRAMS GA AUDITS DA NUC. SITE GA NONCONFORMANCE CONTROLS G INTERNAL AUDITS -

INSPECTIONS  !

ADMIN SERVICES]

4 p g gg _._ SUPPLIER AUDITS -

AUDITS 4 EVALUATIONS i

REVIEWS ISI/NDE i

I b

h 4

0 9

S E

C I Y S N

R E R V C N L O S O I W G ES E

I R E T E T D C hY C I I N N E V MT F O P E I E C S R L D N A I U

Q S

M A

R RG OO TR CP E

RY IT DI L

A U

Q S

M /

E SS T T NT L N RS ON AS EY T EY IE MT R GS TM NT EI O A AS RI RL P NY VS ED UA P AT RE TU CU U MI ES NA OQ S I R L SS A BA P U O Q

A MEETING SUFMRY DISTRIBUTION:

. . . I Docket' NRC PDR Local PDR PD21 r/f E. Adensam Project Manager Lester L. Kintner OGC-B E. Jordan J. Partlow NRC Participants ACRS (10) hRC PARTICIPANTS John Mathis Gus Lainas Elinor Adensam Poss Butcher Lester Kintner I

l i

1 1