ML20034A851

Forwards Summary of 900312 Mgt Meeting to Discuss Licensee Self Assessment of Overall Performance at Plant

ML20034A851
Person / Time
Site:	Summer
Issue date:	04/04/1990
From:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Bradham O SOUTH CAROLINA ELECTRIC & GAS CO.
References
NUDOCS 9004240434
Download: ML20034A851 (57)

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? lAPR:041990 s r l i . Docket No. 50-395-1 License No. NPF-12: l

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~ South Carolina Electric &l Gas' Company: L ATTN: - Mr. ' O. S; Bradham j

Vice President, Nuclear OperationsL

Virgil C. Summer. Nuclear Station-'

P. 0. Box 88 .j .Jenkinsv.ille,:SC 29065-f Gentlemen:.

SUBJECT:

MANAGEMENT MEETING

SUMMARY

--V.C. SUMMER l

This-letter refers to the Management Meeting held;at:yourf request 1on, March 12,-. 1 1990. This meeting' concerned activities authorized for. your..V.- C.J Summer- - facility.. The. issues discussedtat this meeting: related.to your self assessment of overall performance. Inacc'ordancewith10CFR'2.790',-.acopy.ofthislhterandLitlenclosures'will~ d be placed in the-NRC Public Document Room. Should you have any questions concerning this letter,-please' contactL us.: i l ' Sincerely. Original Signed;by y Charles'W.-.liehl./for: M Luis A..Reyes, DirectorL Division of Reactor. Projects:

Enclosures:

1. Management Meeting Summary' 2. List of Attendees i 3. Handout j cc w/encls: i J. L. Skolds, General-Manager <.W Nuclear Plant Operations ) Summer Nuclear Station 1 ,P. O. Box 88 (Mail Code 300) j Jenkinsville, SC '29065 (cc~w/encls cont'd - See page 2) l l l d 9004240434 900404' T" \\\\\\ l PDR ADOCK 05000395 4 L Q-PDC C6Yh 4 a

3 =o .4 South Carolina Electric = and Gas Company 2: - APR.041990! (ccw/encisicont'd) A.. R. Koon, Jr.,: Managar sNuclear Licensing: Summer Nuclear Station ~Pe0. Box 88--(Mail'CodeL612); Jenkinsville, SC 29065 J. B. Knotts,-Jr - = Bishop', Cook,.Purcell &-.Reynolds '1400 L Street, NW iWashington,-D. C'.- - 20005-3502. -R. E. Rainear Executive-Vice President. -South Carolina Public Service Authority. - P. 0.1 Box'398 Moncks-Corner.,SC, 29461-0398:. Chairman, Fairfield County Council P.,0. Box ~-293 'Winnsboro, SC 29180 Attorney' General 1 Box'11549. Columbia, SC 29211-q Heyward G. Shealy, Chief Bureau of Radiological Health-South Carolina-Department of Health-- and Environmental Control 2600 Bull-Street Columbia, SC 29201 .I bec w/encis: J. J. Hayes, NRR Document Control Desk -NRC Resident Inspector U.S. Nuclear Regulatory Commission j -Route 1, Box 64 Jenkinsville,.SC 29065 u l l u

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o. j f 7 .5 [ ENCLOSURE 1 MANAGEMENT MEETING

SUMMARY

l A Management. Meeting.was held in the Region ~ II' 0ffice on March 12, 1990 tox discuss the licensee's self assessment of - overall performance > at the - V.'! C' Summer Nuclear Station.. 'j The.) licensee opened:the meeting-with:an overview of. performance which included accomplishments from.1989 through) the present. -. Management strategiesL: and.) enhancements to continue improvements to - safety and performancei were-- also: discussed.- Plant operations performance was; addressed' by, the licensee 1 and inc1Eded a -discussion of.recent trends. 'In ' addition specific areas: which the-licensee ' determined'a need for improvement were discussedL The licensee: explained their =t approach ' to improvel procedures, drawing - legibility and : labeling plant: equipment. ~ ~ [ The area 'of procedure compliance' was addressed at -length bylthe' licensee in - l response to recent trends in -events related - to plant personnel: failing1to follow procedures. i The licensee-discuss'ed - staffing increases ~ being implemented; and qualification - requirements for engineering and operations personnel.- 1 The. scope of the. Spring 1990 refueling: outage was. discussed at some; length.-- ~ ~ The licensee closed the discussion by addressing long term goals and:a proposed - time frame for steam generator replacement and condenser-upgrades. ~ l k t t = 1

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4; ENCLOSURE 2 -LIST 0F ATTENDEES South Carolina Electric?and Gas Company O. S. Bradham, Vice. President Nuclear Operations-J. L'. Skolds, General Manager Nuclear Operations D. R.. Moore, General. Manager Engineering. Services) K. W.-- Nettles, General Manager Nuclear Safety - -U. S. Nuclear Regulatory-Commission S. D. Ebneter,-Regional Administratorf.. C.W.Hehl,DeputyDirector,DivisionofReactorProjects(DRP) A.F.Gibson, Director,DivisionofReactor: Safety-(DRS). E. Merschoff,' Deputy Director,=DRS D. M. Verrelli, Chief, Reactor Projects Branch 1. DRP D. M. Collins, Chief, Emergency Preparedness and Radiological' Protection Branch,-Division.of Radiation Safety and Safeguardst(DRSS) W. E. Cline, Chief, Nucle'ar Materials Safety. and Safeguards Branch, DRSS-J. J. Hayes, Project Manager,--Office of' Nuclear Reactor-Regulation (NRR). F. S. Cantrell, Chief, Reactor Projects Section 1B, DRP F. Jape,: Chief, Quality Performance Section, DRS P. Kellogg, Chief, Operational Programs Section, DRS 1 R. L. Prevatte, Senior Resident Inspector'- Summer, DRP-- Ji L.-P. Modenos, Resident-Inspector - Summer; DRP P. A. 'Balmain, Project Engineer,- DRP - 1, R. W. Wright, Reactor Inspector, 'DRS L. P. Zerr, Technical Intern, NRR j 1 q 3 1, Jl

ENCLOSilRE 3 4 il i V. C. SUMMER NUCLEAR STATION l l PERFORMANCE REVIEW l FOR THE 1 L U. 5. NUCLEAR REGULATORY COMMISSION i i l i > CHALLENGES i i i l > INITIATIVES i > RESULTS l ? PRESENTED: MARCH 12,1990 q ATLANTA, GEORGIA 4 ) SOUTH CAROLINA ELECTRIC & GAS COMPANY NUCLEAR EXCELLENCE - A SUMMER TRADITION! i i e 4 ~..,,--,,,,.-..,..,.,,.,_,m,.,-,-,,-,,,,,,w, ,-w,ve,

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i TABLE OF CONTENTS section Tab-INTRODUCTION

'1

0. 5. Bradham Vice President, Nuclear Operations -

N U C LE A R PLANT OPE R ATION S............................ 2 I J. L Skolds General Manager Nuclear Plant Operations ENGIN E ERING SERVICES.................................. - 3 s D. R. Moore General Manager Engineering Services. NUCLEAR SAFETY 4 i K. W. Nettles General Manager Nuclear Safety S U M M A R Y............................................... 5 O. 5. Bradham Vice President, Nuclear Operations APPENDIX A: Station Photograph Nuclear Operations Division Senior Management Organization Chart Performance Factors and Goals Principles For Excellence General Employee Training Cutaway i i

...gm.._.. -.,. ~. - - p l l NUCLEAR OPERATIONS DIVISION i [ INTRODUCTION \\ l O. S. BRADHAM VICE PRESIDENT NUCLEAR OPERATIONS L

o L AGENDA i r i ~ e INTRODUCTION Ollie Bradham Vice President, Nuclear Operations o e NUCLEAR PLANT OPERATIONS-i Jack Skolds - 1 General Manager-l Nuclear Plant Operations ~ l o ENGINEERING SERVICES 1 L -Dave Moore General Manager Engineering Services e NUCLEAR SAFETY Ken Nettles General Manager Nuclear Safety o

SUMMARY

Ollie Bradham Vice President, Nuclear Operations 1

1 l 1 ACCOMPLISHMENTS DURING 1989 ] e-COMPLETED PROFESSIONALISM SELF-ASSESSMENT e COMPLETED NUCLEX EVALUATION-l i e APPROVAL TO HIRE 103 ADDITIONAL PERSONNEL e ACHIEVED BUDGET GOALS FOR 1989-1% UNDER O & M 2% UNDER. CAPITAL i e 2 OF 3 UNIT INCENTIVE GOALS' ACCOMPLISHED I e ROOT-CAUSE ANALYSIS PROGRAM IMPROVEMENT i l PRESSURIZER SAFETY VALVE ISSUE-o EHC PROBLEMS e INDUSTRIAL SAFETY RECORD FEBRUARY 21,1990-l

a. : -

j INDUSTRIAL SAFETY-STATISTICS l e LAST LOST TIME CASE - MAY 2,1989 e NUMBER OF DAYS SINCE LAST LOST TIME CASE -296(2/21/90) e TOTAL' NUMBER SAFE MANHOURS WORKED' SINCE LAST LOST TIME CASE -1,000,484 -VCSNS SAFETY RECORDS-e THE MOST CONSECUTIVE DAYS WORKED WITHOUT A LOST TIME INJURY - 635 DAYS-e THE MOST MANHOURS WORKED WITHOUT A-LOST TIME CASE - 1,804,328(10/86 THRU 4/88) MAKE EVERY DAY, A SAFE DAY IN 1990 1 LET'S MAKE IT 2,000,000! l

STRATEGIES FOR ENHANCING EXCELLENCE o EXECUTIVE DIRECTION AND i CONTROL e MANAGEMENT-EFFECTIVENESS e IMPROVE PLANT PERFORMANCE-i e OUTAGE' PERFORMANCE - ENHANCEMENT j e LONG-RANGE PLANNING e HUMAN RESOURCE DEVELOPMENT s e NOD-EXTERNAL RELATIONS e PROGRAM ENHANCEMENT l I

STRATEGIES FOR ENHANCING EXCELLENCE 1 L IMPLEMENTATION PLAN 1 l l e STRATEGY MANAGERS ASSIGNED IN DECEMBER e e COMMUNICATE NUCLEX STUDY RESULTS TO EMPLOYEES e PRIORITIZE STRATEGIES AND GOALS e STRATEGY MANAGER ACTION PLANS DEFINED BV JUNE 30,1990 e IMPLEMENT APPROVED WORK PLAN e PERIODIC PROGRESS REPORTS TO STRATEGY j TEAM, EMPLOYEES, AND CORPORATE-l MANAGEMENT I e ASSESSMENT OF EFFECTIVENESS AFTER WORK PLAN COMPLETION AND ANNUALLY THEREAFTER f I i

NUCLEAR PLANT OPERATIONS e OPERATIONS-e MAINTENANCE e SCHEDULING & MODIFICATIONS e SECURITY l e CHEMISTRY & HEALTH PHYSICS e EDUCATION & TRAINING i a

l J. L. SKOLDS -

GENERAL MANAGER

PLANT OPERATIONS e PLANT PERFORMANCE e PLANT OPERATIONS i e RADIOLOGICAL CONTROLS e MAINTENANCE / SURVEILLANCE e EMERGENCY PREPAREDNESS e SECURITY e TRAINING e PROCEDURE COMPLIANCE / PERFORMANCE IMPROVEMENT l i

PLANT PERFORMANCE: JANUARY 1,1989 - FEBRUARY 28,1990 UNIT AVAILABILITY: 83.5 % UNIT CAPACITY FACTOR: 74.0 % FORCED OUTAGE RATE: 16.45 %

.e PLANT OPERATIONS i 1 Previous SALP Rating: -2 Areas Needing improvement: o Procedures q e Drawing Legibility i e Labeling e Procedure Compliance e ReactorTrips o EOPs e Watchstanding Administrative Controls 1

= h PLANT OPERATIONS (cont'dD 1 Actions: e Procedure Reviews /Walkdowns

• Upgraded Drawings e Labeling Program
• Personnel Error Reduction Program 1

L e EOP Upgrade e Test Group-j e Operations Standards e improved Watchstanding Administrative Controls i i t L s 4 i

RADIOLOGICAL CONTROLS-Previous SALP Rating:- 1 p Areas Needing improvement: o Collective Dose Reduction e Reduction of Source. e PersonnelContaminations i Actions: e improved ALARA Committee l e Elevated Priority of ALARA Planning-e Emphasized Worker Accountability e FuelInspection Planned for Refuel 5 e Emphasized PCTechniquesinTraining e Stricter Controls for Spills e Established More Ambitious Goals for.1990 e improved ALARA Suggestion Program

l MAINTENANCE / SURVElLLANCE 7 Previous SALP Rating: 1 l L Areas Needing improvement: i e First Line Supervisory involvement l.; e Procedure Compliance / Personnel Performance e Worker Knowledge L Actions: ( e -Shop Supervisory involvement

• Personnel Error Reduction Program l

e-Improved Training i e Technical Manualimprovement j I* e improved Procedures o Reliability Centered Maintenance p e Test Group 1 } S

1 l EMERGENCY PREPAREDNESS i Previous SALP Rating: 2 l I Areas Needing improvement: e Training o Classification

• Communications f

Actions:

• Development of Training Matrix

{ i e increased QA Surveillance e Conducted Additional Training for SS/IED/EDs e increased Communications Drills e Tested Back-Up EOF e Moving EOF 1 e Development of Emergency Plan DBD e increased State and LocalInterface e increased Staff

j 1 l SECURITY i Previous SALP Rating: 2 (declining) l 1 1 Areas Needing Improvement:

• Management of Security Operations e Personnel Access Control e Hardware Actions:

o New Manager, Nuclear Protection Services e increased Senior Management involvement e improved NRC Communications e Improved Training on Safeguards Events e Increased Supervisory involvement e De'veloped Security Shift Leader Handbook e improved Badge issuance Procedure

• Adding Cameras o Adjusted Cameras - Masking Eliminated e Replaced E-Field

t i l TRAINING i i 1 Areas Needing Improvement: e Shortage ofinstructors 1 e Development of New Test Format 1 Actions:

• Added 9 Positions e 21 of 24 Licensed Personnel Passed Requal Exam e 100% Pass Rate for New ROs/SROs I

e 9

1 J PROCEDURE COMPUANCE/ PERFORMANCE 1 IMPROVEMENT l 4 l Indicators: 1 l e Recent increase in frequency of personnel errors l

• Procedure noncompliance o Procedures generally adequate Actions:

,i e NUCLEX e Trending Programs e Extensive Communications l 1

• General Managerinvolvement I

e Identification of problems in each group e Vertical slice of organization e Establishment of monitoring system e Division goal j e Emphasize Principles of Excellence I I

i i i i ENGINEERING SERVICES i DESIGN ENGINEERING SYSTEMS & PERFORMANCE ENGINEERING 1 l e CORE ENGINEERING & l NUCLEAR COMPUTER SERVICES l e MATERIALS & PROCUREMENT ENGINEERING l D. R. MOORE j GENERAL MANAGER 4 .,,-__.,,..,.._,.r. ,,.y... ..m.',,,,.,m_,,.._,,,,my,- ., -y. e--ww..,,,,,,,,,...

I l ) l TECHNICAL SUPPORT 1 l (Engineering Services) l Previous SALP Rating - 2 l l t e Staffing Status l l e System Engineer Program Status j 7 j e Steam Generator Status i e Engineering Issues l l Problem Identification l l Design Basis / Licensing Basis Documents Drawing Legibility i l IPE/PRA Milestones l j l 0 i .~.

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e o STAFFING LEVEL DESIGN ENGINEERING PREVIOUS INCREASE PRESENT MANAGEMENT / SUPERVISION 5 0 5 ENGINEERS 21 7 28 SPECIALISTS 9 5 14 TOTAL 35 12 47 NEW POSITIONS-(03/12/90) FILLED 6 PROCESSING 3 OPEN 3

e STAFFING LEVEL Systems & Performance Engineering Previous increase Present Management / Supervision 4 0 4 Engineers 19 11 30 Specialists 0 5 5 Total 23 16 39 New Positions-(3/12/90) Filled 3 Processing 8 Open 5 _.__m..aL.

1 i l i l SYSTEM ENGINEER QUALIFICATION STATUS l t ~ 13 Engineers Fully Qualified on One (1) System e 4 Engineers About to Qualify on First System e i 5 Engineers in Process on First Qualification j e j i 1 e Qualified Engineers Working on Other Systems l i l 46 of 84 Engineers Completed Nuclear Technical Training i l 35 of 84 Have Professional Engineering Licenses j 1 i ..... ~.. --,-~..,.....-.. - ~-..,-.,- ~.-

REFUEL 4 (RF4) STEAM GENERATOR l TUBE PLUGGING S/G A S/G B S/G C TOTAL

1. PLUGGED 117 293 129 5'39 l

BEFORE RF4 (2.5%) (6.3%) (2.8%) (3.8%) l 4 l

1. PLUGGED l

DURING REFUEL 4 (3.9%) (5.0%) (3.7%) .(4.2%) )

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1. OF PLUGGED TUBES i

RECOVERED DURING 17 19 0 36 RF 4 (F*, MIS PLUGS) j TOTAL # PLUGGED 280 507 304 1991 ) l (6.0%) (10.9%) (6.5%) (7.8%)

1. MEETING F*

97 203 69 369 CRITERIA DURING RF 4 (2.1%) (4.3%) (1.5%) (2.6%)

1. OF RF 4 PLUGGED 95 77 51

• • 233 T'

"^ A (2.0%) (1.6%) (1.1%) (1.7%) CA DTS l " 39.6% (233/588) OF THE TUBES PLUGGED DURING REFUEL 4 (FAILED l TO MEET F* CRITERI A) WOULD H AVE BEEN CANDIDATES FOR MEETING THE L* CRITERI A. l 1 \\ - ~

i STEAM GENERATOR PROJECT I RF 5 WORKSCOPE I SGA SGB SGC ) TASK \\ HL CL HL CL HL CL i TURE ECT 4394* 4167* 4372* PLUGECT 275 194 302 110 d PULL PLUG *

• 192 0

51 0 279 0 PAP 5 0 111 0 2 0 i PLUG *

• 299 107 148 97 403 124 I

$LEEVE** 100 100 l STABILl!E U BEND 1 1 5 l VERIFICATION Yes Yes Yes Yes Yes Yes l INSPECTION FOREIGN OBJECT SEARCH & RETRIEVALIN SIG "C"

• Approximately 23 % of these tubes will be inspected from the hot leg tubesheet over the U bend to the top support plate of the cold leg.
• Projected Numbers.

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PROBLEM IDENTIFICATION / RESOLUTION e STEAM BREAK INVESTIGATION e CHILLER - SERVICE WATER FLOW RATES (CHILLER WATER)- PART 21 e ROOT CAUSE EVALUATION - DC GROUND CUMULATIVE EFFECTS -IEN 88-86 SUPP.1 e ELECTRICAL SSFI-DEGRADED VOLTAGE CALCULATIONS e SERVICE WATER SSFl-MODIFICATION TO FIX POTENTIAL FLOODING e PRESSURIZER SAFETY VALVE EVALUATIONS e IDENTIFICATION / RESOLUTION OF PROBLEMS RESULTING FROM JULY 11 PLANT TRIP i

i f.. i DESIGN BASIS DOCUMENT (DBD) PROGRAM STATUS t i-DBDs ISSUED Thru 1989 24 l 4 l i l DBDs UNDER DEVELOPMENT 11 DURING 1989 l (To Be Issued During 1990) LICENSING BASIS DOCUMENT (1990) 1 d DBDs PLANNED (1990 - 1991) 12 l 4 DBDs PLANNED (1992) 7 DBD PROGRAM TOTAL 53 j i

l l DRAWING CONTROL PROGRAM t i ENHANCEMENTS REVISED PROGRAM TO ENSURE: r l 1 i l 9 Correct drawing / revisions Maintained in Control Room e All Control Room Essential Drawing are Supplemented with Interim Drawings during Modification Process TIGHTENED STANDARDS FOR DRAWING LEGIBILITY: i l e Level 1 - 100% Legibility as Determined by Doc, Control l e LevelII - Legibility Requirements Determined l by User l e Levelill - Acceptable As-Is l INSTALLED INTERGRAPH SYSTEM:

• Drawings will be maintained by Computer l

e Eliminates further Deterioration of Drawing e Used for Drawing Enhancements l i I m,

i l lPE TASKS i ) 1. PROJECT MANAGEMENT l 2. INFORMATION COLLECTION l 3. DATA COLLECTION & DATA BASE 4. INITIATING EVENTS ) 5. PLANT DAMAGE STATES i 6. SUPPORT STATE MODEL & QUANTIFICATION 7. EVENT TREE DEVELOPMENT I 8. SYSTEM DESIGN DOCUMENTATION i 9. FAULT TREE DEVELOPMENT l 10. SYSTEMS INTERACTION EVALUATION l 11. HUMAN RELIABILITY ASSESSMENT 12. FAULT TREE QUANTIFICATION 13. ACCIDENT SEQUENCE QUANTIFICATION 14. INTERNAL FLOODING ASSESSMENT 15. RECOVERY ACTION EVALUATION 16. EVALUATION OF SEQUENCE ANALYSIS 17. SENSITIVITY & IMPORTANCE ANALYSIS 18. IMPAIRED CONTAINMENT ANALYSIS 19. CONTAINMENT SYSTEMS ANALYSIS t 20. CONTAINMENT STRUCTURAL ASSESSMENT 21. CONTAINMENT EVENT TREE 22. SOURCE TERM ANALYSIS & EVALUATION 23. EVALUATION OF IPE RESULTS 24. PROJECT DOCUMENTATION 25. INDEPENDENT REVIEWS 26. PROJECT REVIEW 27. IPE SUBMITTAL REPORT _..-....__....--_..--_.,...__...,.,,..,,._,,,_m._,...,_.,, ,., _, ~........ -... -,,., _... _,.

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i l l l ) NUCLEAR SAFETY t i e TECHNICAL OVERSIGHT I e QUALITY SYSTEMS i e CORPORATE HEALTH PHYSICS & ENVIRONMENTAL PROGRAMS e NUCLEAR LICENSING .i i i l-l i K. W. NETTLES l GENERAL MANAGER 4 w 't )

i I SAFETYASSESSMENT QUALITY VERIFICATION l PREVIOUS SALP RATING: 2 i o Trending Overview r e Safety System Functional Reviews i l e Root Cause Analysis l ALARA Review Initiatives e Operating Experience Status NOD Plant Management Overview e Licensing Status e Staffing N

1 l TRENDING OVERVIEW i l i o Quality-Based Trending l l l Audit / Surveillance Findings l Programmatic Concerns l I NCN's Work Practice Observations i Technical-Based Trending l NPRDS l NCN's l R&R Logs j 151 Pump Maintenance [! Vibration of Rotating Equipment Equipment Aging and Performance Trending i Off-Normal Occurrences 1 i j Station Battery inspections l I e Future initiatives l Integration of AllTrending Programs Strengthening of Root Cause Analysis l

L i i j SAFETY SYSTEM FUNCTIONAL REVIEWS (SSFR'S) \\ e SSFR'S Completed ) l ) 1 Emergency Feedwater Emergency Power Service Water DG Services l Component Cooling Water HVAC o SSFR's Scheduled For 1990 l Residual Heat Removal RB Structure and Containment l Systems l l l e SSFR's Scheduled Beyond 1990 [ Safety injection 1 i Chemical and Volume Control Reactor Make-up Water Reactor Protection Control System Rod Control i Fire Service 4 i . ~.

i ) l SSFR STATUS OPEN CLOSED TOTAL-Emergency Feedwater 7 33 40 ? l 1 Emergency Power 9. 22 31 i i Service Water 13 14 27. l l l Diesel Generator 10 6 16 1 Component Cooling 13 3 16 1 Air Handling 18 0 18 4 i k s j: -,,,,----,..,,.,,n--n~. ,...n.,..+.n..,... ---....-,n ..,,,.--,.,-n- .,...~.-~.-.. -.,..,....,.. --n,

\\ SSFR STATUS EFW EPS SWS DG CCW HVAC l l l l MODIFICATIONS Hardware 2 4 4 4 1 4 i l Design Documents 6 13 12 9 7 6 i Testing and/or. 23 14 10 6 11 9 Procedural Upgrading j i i i Software (FSAR, Tech. 7 5 1 1 0 3 l Spec., etc.) i i No Changes 7 5 3 1 0 2 1 l 'l 1

b l. j i j l Roor CAUSE ANALYSISISSUES 1 i 1 e Tra..ining i l e Root-Cause Analysis Manual l l e HPES Initiative 1 e MRB Root Cause Analysis Team Actions 4 i e Proactive Posture l l { j } i b 1 l i ) p _____-_.-_______________..__m.._____.........__.._.__.._..,...,__m._.. m. . - c,,,, -,. ..,v..-.

i L l i i CHP ALARA REVIEWINITIATIVES i i L i i e RFO #5 Continuous ALARA Review of. Activities l i e Inter-Utility Participation in ALARA l Reviews l e Performance Based ALARA Reviews I u e increased Technical Support p 3 i ?

L ^ OPERATING EXPERIENCE l e Current Status -Industry Issues I i 48 - Screening / Evaluation 80 - Implementation 128 Total Backlog e Averages For Past Twelve (12) Months i 17.8 - Received Per Month. 18.1 - Closed Per Month e Initiatives Strengthen In-House Program Continue Reduction of Backlog

PLANT MANAGEMENT i. OVERVIEWINITIATIVE j i l \\ l l e VP/GM's Periodic Overview of Plant i Operations / Trends Performance Indicators Trending Overview l o Programs and Hardware L e Assess Overall Plant Performance e Identify Initiatives e Proactively Pursue improvements l o l .. _..,. _ _ _ _ _. _, _..., _.. _. _ _.. _, _ -.... _, ~.. _.

LICENSING STATUS e LER's e Violations e Refueling Outage #5 Submittals Eight(8) Submittals 5/G Tube Sleeving F* Criteria Renewal RTD By-Pass Manifold Elimination e Licensing Basis Document - NSAC125 License Basis Design Basis Adequate 10CFR50.59 Evaluations a

i 1 t e LER COMPARISON n i 1 -i X F 1 40 t i 35 33 32 V V/' I g/ 27 l 3 / j// .T 25 1

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0 {' Westinghouse National V. C. Summer . V. C. Summer (last Report) Average (Last Report) (01/01/89 -02/28/90) (Last Report).

. 4 V. C. SUMMER LERs i 't 20 Present i (01/01/89 02/28/90) ,.t Last Report. i 15 34 N 4 11 a 10 .E E 7 w:, '~ 6 6 j. Personnel Design /Const. Comp Failure Other-4

i VIOLATIONS

SUMMARY

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STAFFINGINITIATIVES e Quality Systems Four(4) QA Engineers Improved Technical Expertise Quality-Based Technical Support Performance Based Auditing Support Schedule - 4/90 o Nuclear Licensing Three (3) Licensing Engineers Improved Technical Review of Submittals Increased Technical involvement in Licensing issues Schedule -In Progress - 12/90 o Operating Experiences (OE) Two (2) Engineers and Two (2) Specialists - Further Reduction of OE Backlog Improved in-House OE Program Trending Root Cause Analysis Schedule -In Progress - 12/90

l e b NUCLEAR OPERATIONS DIVISION 4 i r i l

SUMMARY

L i 1 l 1 O. S. BRADHAM VICE PRESIDENT l-NUCLEAR OPERATIONS l

1 t i L 1990 PLUS INITIATIVES p i 1 l l e IMPLEMENT STRATEGIES FOR ENHANCING l l EXCELLENCE j i l STRENGTHEN OUR-MANAGEMENT OVERVIEW. TRENDING PROGRAM-TO ASSURE PRECURSORS i ARE IDENTIFIED AND ADDRESSED e STEAM GENERATOR ~ REPLACEMENT CONTEMPLATED FOR MID TO LATE 90's e UP RATE UNIT TO " STRETCH-POWER" OF 2,910 MWT AND 990 MWE DURING OR AFTER STEAM l GENERATOR REPLACEMENT l L e CONDENSER UPGRADE AND REPLACEMENT PLANNED FOR EARLY 90's l o I i 'l l 1 1

.t I l CONCLUSIONS 1 \\ I l e INITIATIVES PRODUCING POSITIVE BENEFITS l .? l CONTINUE AGGRESSIVE APPROACH TO i. PROBLEM-SOLVING l e CORPORATE MANAGEMENT ATTENTION AND SUPPORT. VERY GOOD a e COMMITTED TO ACHIEVING EXCELLENCE o COMMITTED TO ENSURING' REACTOR SAFETY. [ T M

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e. .) aS e SOUTH CAROLNA ELECTRC & GAS CohPANY 1 i NUCLEAR EXCELLENCE y e. n - 0 R, mons 1 d g DMSION i A SUMMER IRADlitONI O S BRADHAM l VICE PRESIDENT NUCLEAR OPERATIONS l l .i i i I I sw + r-I e - ~. a I J L SKOLDS .M B WILLIAMS D R MOORE M w PETTLES ~ GENERAL MANAER GENERAL MANAGER .GEtERAL MANAGER CeNE#AL MANAGEE~ NUCLEAR PLAbT OPERATIONS ADMINISTRATIVE & SUPPORT SERVICES .ENGItEERING StERVICES tarLEAR SAFETY )

• ADMINISTRATION
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• NUCLEAR LICENSING NUCLEAR COMPUTER SERVICES

.i 4 s, 4 6 co-i 't j G G SOULT M D OUINTON GENERAL MANAGER GENERAL MANAGER OPERATIONS & MAINTENANCE STATION SUPPORT i GOPERATIONS ONUCLEAR PROTECTION -

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SERVICES i MOO 1F ICAi!ONS oct4 MISTRY & *E AL TH [ 6 MAINTENANCE SERVICES. FHYSICS

• NUCLEAR OPERATIOtG EDUCATION & TRAINING
• NUCLEAR TECHNICAL EDUCATION & TRAINING

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1990 T V. C. SUMMER NUCLEAR STATION PERFORMANCE FACTORS AND GOALS i KEEP US IN THE BLUE LOST TIE INJURY RATE $ CAPACITY FACTOR $ W N AUTOMATIC VOLIJE OF SOLID $ REFUELING OUTAGE $ i 1990 GOAL 5.2 (PERCENT) SCRA>S WHILE CRITICAL RAD WASTE BREAKER TO BREAKER j (si INJURY) (EXC. REFUELING OUTAGE) 1993 COAL s 2 1990 GOAL's 195 1990 GOAL s 65 DAYS 1990 GOAL 2 88% CUBIC METERS-2.00 too-5< 2 e O-MARCH 23-MAY 26 'JfsiAJJindid

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