ML18151A968
| ML18151A968 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna |
| Issue date: | 03/27/1991 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 9106110063 | |
| Download: ML18151A968 (92) | |
Text
~9
MAR 2 7 1991 Docket Nos. 50-280, 50-281, 50-338, and 50-339 License Nos. DPR-32, DPR-37, NPF-4, and NPF-7 Virginia Electric and Power Company ATTN:
Mr. W~ L. Stewart Senior Vice President - Nuclear 5000 Dami ni on Baul evard Glen Allen, VA 23060 Gentlemen:
SUBJECT:
MANAGEMENT MEETING
SUMMARY
This letter refers to the Management Meeting held on March 15, 1991, at the Region II office.
The meeting concerned a discussion of your Integrated Nuclear Safety Assessment Program and an update of your Configuration Management Project.
A list of attendees, a meeting summary, and a copy of your handouts are enclosed.
In accordance with section 2. 790 of the NRC 1 s Rules of Practice, 11 Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in.the NRC Public Document Room.
Should you have any questions concerning this letter, please let us know.
Enclosures:
- 1.
List of Attendees
- 2.
Meeting Summary
- 3.
Handout - Safety Assessment
- 4.
Handout - Configuration Management cc w/encls:
E. W. Harrell Vice President - Nuclear Operations Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 cc w/e~cls cont 1 d:
(See page 2) 9106110063 910327 PDR ADDCK 05000280 P
PDR Sincerely, Original Signed by Luis A. Reyes Luis A. Reyes, Director Division of Reactor Projects
Virginia Electric and Power Company cc w/encls cont'd:
J. P. O'Hanlon Vice.President - Nuclear Services Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 M. R. Kansl er Station Manager Surry Power Station P. 0. Box 315 Surry, VA 23883 M. L. Bowling, Jr., Manager Nuclear Licensing Virginia Electric & Power Co.
5000 Dominion Boulevard Glen Allen, VA 23060 Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, VA 23683 W. T. Lough Virginia Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, VA 23209 Michael W. Maupin Hunton and Williams P. 0. Box 1535 Richmond, VA 23212 C. M. G. Buttery, M.D., M.P.H.
Department of Health 109 Governor Street Richmond, VA 23219 Attorney General Supreme Court Building 101 North 8th Street Richmond, VA 23219 G. E. Kane, Station Manager North Anna Power Station P. 0. Box 402 Mineral, VA 23117 (cc w/encls cont'd - See page 3) 2 MAR 2 7 1991
Virginia Electric and Power Company (cc w/encls cont'd)
Executive Vice President Old Dominion-Electric Cooperative Innsbrook Corporate Center 4222 Cox Road, Suite 102 Glen Allen, VA 23060 William C. Porter, Jr~
- county Administrator Louisa County P. 0. Box 160 Louisa, VA 23093.
Patrick A. O'Hare Office of the Attorney General Supreme Court Building 101 North 8th Street Richmond, VA 23~19 Commonwealth of Virginia bee w/encls:
Document Control Desk P. Fredrickson, RI!
L. Engle, NRR B. Buckley, NRR NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 78-A Mineral, VA 23117 NRC Resident Inspector U.S. Nuclear Regulatory Commission Routes 1, Box 166 Surry, VA 23883 RII:q~
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1 MAR % 7 1991 I
. I
I I
ENCLOSURE 1 MANAGEMENT MEETING LIST OF ATTENDEES Virginia Electric and Power Company (Virginia Power)
F. Moore, Vice President, Nuclear Engineering Services J. O'Hanlon, Vice President, Nuclear Services M. Bowling, Manager, Nuclear Licensing and Programs A. Price, Assistant Station Manager - Surry J. Stall, Assistant Station Manager - North Anna R. Driscoll, Manager, Quality Assurance - Corporate D. Benson, Manager, Configuration Management Nuclear Regulatory Commission - Region II S. Ebneter, Regional Administrator, Region II (RII)
J. Milhoan, Deputy Regional Administrator, RII L. Reyes, Director, Division of Reactor Projects (DRP), RII A. Gibson, Director, Division of Reactor Safety (DRS), RII M. Sinkule, Branch Chief, DRP, RII P. Fredrickson, Section Ch~ef, DRP, RII F. Jape, Section Chief, Test Programs Section (TPS), DRS, RI!
G. Hallstrom, Reactor Inspector, TPS, DRS, RII Nuclear Regulatory Commission - Headquarters H. Berkow, Director, Project Directorate II-2 (PD II-2), NRR G. Imbro, Chief, Special Inspections Branch, NRR
ENCLOSURE 2 MEETING
SUMMARY
An NRC and Virg1nia Power management meeting was conducted at the Region II office on March-15, 1991, to discuss the licensee's Integrated Nuclear Safety Assessment Program and a status review -of the Configuration Management Project.
The Regional Administrator opened the meeting by stating that" the NRC was interested in licensee's safety assessment capability.
The Vice Presi_dent, Nuclear Services, provided opening remarks for Virginia Power.
The safety assessment presentation was then conducted, using a handout, enclosure 3.
The Assistant Station Manager for both Surry and North Anna and the Corporate Quality Assurance Manager provided infonnation on the methodology and content of.the various safety assessment programs.
Discussion took place on the mechanism for changing colors on the various windows and also on what effort is being made to ensure that all levels Qf management do not become defensive in their self-evaluations.
The presentation was closed by Virginia Power stating that the primary purpose-of this program*will continue to be self-improvement.
The Configuration Management Project was then.discussed by the Vice President, Nuclear Engineering Services, and the Manager, Configuration Management.
A handout, enclosure 4, provided status information on this project.
The NRC management closed the meeting by thanking Virginia Power for both presentaticins.
ENCLOSURE 3 VIRG.INIA-POWER INTEGRATED NUCLEAR SAFETY ASSESSMENT PROGRAM MARCH 15, 1991
AGENDA OPENING REMARKS INTEGRATED NUCLEAR SAFETY ASSESSMENT PROGRAM NORTH ANNA NUCLEAR SAFETY ASSESSMENT
- SURRY NUCLEAR SAFETY ASSESSMENT STATE OF QUALITY CONCLUDING REMARKS J.P. O'HANLON M. L. BOWLING J. A. STALL J. A.*PRICE R.* F. DRISCOLL J.P. O'HANLON
OPENING REMARKS J.P. O'HANLON VICE PRESIDENT - NUCLEAR SERVICES
1991 NUCLEAR BUSINESS PLAN PURPOSE - TO COMMUNICATE MISSION, VISION, OBJECTIVES, STRATEGIES, AND SPECIFIC GOALS MISSION - TO OPERATE SURRY AND NORTH ANNA SAFELY, RELIABLY, AND EFFICIENTLY OBJECTIVES AND STRATEGY NUCLEAR AND INDUSTRIAL SAFETY HUMAN RESOURCES AND PROFESSIONALISM REGULATORY COMPLIANCE PERFORMANCE COST MANAGEMENT GOALS AND PERFORMANCE MEASURES
INTEGRATED NUCLEAR SAFETY ASSESSMENT PROGRAM M. L*. BOWLING MANAGER - NUCLEAR SAFETY AND LICENSING
NUCLEAR SAFETY POLICY BASIC PRINCIPLES
- CORE SAFETY / INTEGRITY PREVENTION OF EVENTS
NUCLEAR SAFETY POLICY (continued)
GUIDELINES HIGHEST STATE OF AVAILABILITY OF TECH SPEC REQUIRED EQUIPMENT MINIMIZE TIME SPENT IN TECH SPEC LCOs MINIMIZE STATION ACTIVITIES DURING CRITICAL EVOLUTIONS MINIMIZE POTENTIAL TO REDUCE DECAY HEAT REMOVAL OR SHUTDOWN MARGI.NS UFSAR DEVIATIONS SUPPORTED BY 10CFR50.59 EVALUATION CONSERVATIVE INTERPRETATIONS OF TECH SPECS AND REGULATORY REQUIREMENTS ACTIVITIES PERFORMED WITH APPROVED PROCEDURES AND POLICIES LINE MANAGEMENT COGNIZANCE OF PLANT CONDITIONS MANAGEMENTSUPPORTOFSELFCHECKPROGRAM
INTEGRATED NUCLEAR SAFETY ASSESSMENT PROGRAM.
MANAGEMENT PERSPECTIVE REGULATORY PERSPECTIVE QUALITY PERSPECTIVE NUCLEAR SAFETY PERSPECTIVE i
INTEGRATED NUCLEAR SAFETY ASSESSMENT PROGRAM
( continued)
- , MANAGEMENT PERSPECTIVE PERFORMANCE ANNUNCIATOR WINDOWS STAFFING, TRAINING AND QUALIFICATION TRENDS INDUSTRIAL SAFETY TRENDS COMMITMENT MANAGEMENT STATUS REGULATORY PERSPECTIVE NRC INSPECTION REPORT TRENDS INPO AND NRC INDICATOR TRENDS QUALITY PERSPECTIVE.
STATE OF NUCLEAR QUALITY INTEGRATED AUDITING PERFORMANCE BASED ASSESSMENTS/ OBSERVATIONS
INTEGRATED NUCLEAR SAFETY ASSESSMENT PROGRAM (continued)
NUCLEAR SAFETY PERSPECTIVE STATE OF NUCLEAR SAFETY STATE OF SYSTEMS MATERIAL CONDITION DESIGN MARGIN SHUTDOWN OPERATIONS OUTAGE AND STARTUP OPERATIONS PERSONNEL PERFORMANCE TRENDS POTENTIALLY SIGNIFICANT EVENT AND LER TRENDS NUCLEAR SAFETY PERFORMANCE BASED ASSESSMENTS
PER.FORMANCE BASED ASSESSMENTS IN 1990 ISSUE NRC COMMITMENT MANAGEMENT EMERGENCY OPERATION PROCEDURES INSTRUMENT AIR DECAY HEAT REMOVAL AND BLACKOUT POTENTIALL V SIGNIFICANT PLANT EVENTS REACTIVITY MANAGEMENT SITE MAN HOURS 672 1740 468 740 900 440
PERFORMANCE BASED ASSESSMENTS PLANNED IN 1991 ELECTRICAL DISTRIBUTION
- . OPERATIONS MAINTENANCE SYSTEM CONFIGURATION CONTROL LUBRICATION CONTROL ESF ACTUATIONS UTILITY EXCHANGE ASSESSMENT PROGRAM
(.
NORTH ANNA NUCLEAR SAFETY ASSESSMENT J.A.STALL ASSISTANT STATION MANAGER*
NUCLEAR SAFETY AND LICENSING
NORTH ANNA NUCLEAR SAFETY ASSESSMENT PERFORMANCE ANNUNCIATORS AND TRENDS STATE OF KEY NUCLEAR SYSTEMS SHUTDOWN OPERATIONS PERSONNELPERFORMANCETRENDS NRC INSPECTION REPORT TRENDS
PERFORMANCE ANNUNCIATORS AND TRENDS*
NORTH ANNA PERFORMANCE ANNUNCIATOR PANELS QUANTITATIVE EVALUATION CRITERIA TIGHTENING WINDOW COLOR SETPOINTS PANEL COLOR CHANGES THIRD - FOURTH QUARTERS 1990 1990 PERFORMANCE ANNUNCIATOR TRENDS
- *
- SIGNIFICANT WEAKNESS PANELS RED AND YELLOW PANEL CORRECTIVE ACTIONS
Personnel Performance Equipment Performance Program Performance North Anna Performance Annunciator Panel Status for Fourth Quarter 1990 Operation Plant <;:/,:
Equlvunt;. ;*
Avalllllblllty *:*.
.... /**
Operating Program Radlatio.n Protection Program Regulatory Performance Program Maintenance Key Safety System Performance Maintenance Program Emergency eroparedness, Program Training Program Radlolo~lcal NSS Protection RCSAnd Secondary System Integrity Thermal ESF Performance Actuation*
Planning &
Schedl.lling Prdgram lnduatrlal Safety Program Moriagement Po.rformnnco Modification Program Safoty AeNaemenl And Quality Program Engineering Syatem Material Condition Reactor
'Trip*
Procodur*
Program Material*
Program Station Emergency Preparedness Equipmc11t Avallability Chsmlatry Performance Security Program Site Englnaartng Program Red a -Significant Weaknel9 Yellow D -Improvement Needed White O - Satisfactory Green
- Significant Strength
North Anna Performance Annunciator Panel PERSONNEL PERFORMANCE EQUIPMENT PERFORMANCE PROGRAM PERFORMANCE
.4THOTR COLOR 3RD0TR COLOR OPERMING PROGRAM
~NTENANCE MAINTENANCE PROGRAM Panel Color Changes Third - Fourth Quarter 1990 RCSAND SECONDARY SYSTEM INTEGRITY
- !tr.,~~
+::: THERMAL ESF.
. PERFORMANCE ACTU"1'10NS MODIRCMION
.PROGRAM SAFETY ASSESSMENT AND QUALITY PROGRAM SYSTEM MATERIAL
.
- CONDITION.
STRION SITE ENGINEERING
. PROGRAM RED * - SIGNIFICANT WEAKNESS YELLOW O -IMPROVEMENT NEEDED WHITE O -SATISFACTORY GREEN Ill -SIGNIFICANT STRENGTH
1990 NORTH ANNA WINDOWS TREND 250 244 223 200 178 150 100 50 0
North Anna Performance Annunciator Panel 1990 Fourth Quarter Significant Weakness Panels*
ENGINEERING STATION KEY SAFETY SYSTEM EQUIPMENT PERSONNEL PERSONNEL PERFORMANCE:
PERFORMANCE PERFORMANCE:
PERFORMANCE:
ESF ACTUATIONS:
UNIT2 NRC VIOLATIONS LEAS CONTAINMENT UNIT2EDG ISOLATION VALVES PROCEDURE PROGRAM:
PAR BACKLOG
-~ Virginia Power..
Fourth Quarter, 1990
~North Anna Power Statton Local Performance Annunciator Window Report Area Personnel Performance
- Panel Engineering Personnel Performance Color Justification Window No. 3 NBC VIOLATIONS
- 1)
Level IV - Procedures not available after post-DCP trip Area Number Pane I Number
- 2)
Level IV - Inadequate design, EDG stans during undcrvoltage test
- 3)
Non Cited Violation - Procedure not revised, Instrument Air modification has potential for overloading an EDG Documentation Inspection Report Log Criteria GREEN -
No violations WHITE -
1 non-cited violation YELLOW..
1 cited violation or s 3 non-cited violations RED -
- ~ 2 cited violations or > 3 non-cited violations Management Corrective Actions:
1 5
- 1)
- Revised engineering standard for Design Change Package development, STD-GN-0001.
- Revised administrative procedure for Engineering Work Request development (ADMIN 3.7).
- 2)
- Issued Engineering Technical Bulletin (N-37) to advise engineering personnel of this event.
- Advised the Architect Engineer that developed the DCP of Virginia Power concerns. They made -corresponding changes to their design review process.
- Presently evaluating engineering standard STD-GN-0001 for adequacy of instructions related to design reviews. This activity is scheduled to be completed by March 31, 1991.
- 3)
- Issued Standing Order 17 6 to insure containment air compressors do not start following a DBA.
- Revised appropriate procedures to clear standing order.
Page 53
STATE OF KEY NUCLEAR SYSTEMS KEY NUCLEAR SYSTEM SELECTION CRITERIA COLOR ASSIGNMENT-CRITERIA KEY SAFETY SYSTEM PERFORMANCE KEY SAFETY SYSTEM AVAILABILITY
KEY NUCLEAR SYSTEM SELECTION CRITERIA
- IMPORTANCE TO SAFETY
- REGULATORY SIGNIFICANCE IMPORTANCE TO RELIABLE GENERATION IMPACT ON OPERATIONS EFFICIENCY IMPACT MAINTENANCE COST
- RAD WASTE GENERATION/ PERSONNEL EXPOSURE I
COLOR ASSIGNMENT CRITERIA PRIMARY INPUT
- QUARTERLY REPORT OF SYSTEM SUMMARIES RED SIGNIFICANT ACTUAL REDUCTION IN THE MARGIN OF SAFETY YELLOW
- POTENTIAL REDUCTION IN THE MARGIN OF SAFETY OR SIGNIFICANT OPERATIONS/
MAINTENANCE IMPACT WHITE FULLY ACCEPTABLE SYSTEM GREEN
.SIGNIFICANT IMPROVEMENT THAT INCREASES
. THE MARGIN OF SAFETY OR ENHANCES THE OPERABILITY/ MAINTAINABILITY
North Anna Local Performance Annunciator Panel KEY SAFETY SYSTEM PERFORMANCE
RED
- SIGNIFICANT WEAKNESS YELLOW O -IMPROVEMENT NEEDED WHITE O SATISFACTORY GREEN * *
- SIGNIFICANT STRENGTH
North Anna Local Performance Annunciator Panel KEY SAFETY SYSTEM AVAILABILITY RED
- SIGNIFICANT WEAKNESS YELLOW O -IMPROVEMENT NEEDED Status ror Fourth Quarter 19911 WHITE O
- SATISFACTORY.
GREEN
- SIGNIFICANT STRENGTH
North Anna Local Performance Annunciator Panel SYSTEM MATERIAL CONDITION ISTVALVE PROGRAM HEAT TRACING RADIATION MONITORS RED *
- SIGNIFICANT WEAKNESS YELLOW O - IMPROVEMENT NEEDED Status for Fourth Quarter 1994t APPENDIX R EQUIPM~NT CHILLED WATER HEATING VENTILATION &
AIR CONDITIONING RECIRCULATION SPRAY AUXILIARY FEEDWATER INSTRUMENT AIR CFAR WHITE O -SATISFACTORY GREEN
- SIGNIFICANT STRENGTH
SHUTDOWN OPERATIONS.
TECHNICAL SPECIFICATIONS FREQUENTL V DO NOT APPLY EMERGENCY OPERATIONS PROCEDURES ARE NOT APPLICABLE NECESSARY MAINTENANCE REQUIRES KEY SAFETY BARRIERS TO BE REDUCED INCREASED ATTENTION REQUIRED FOR CRITICAL PLANT PARAMETERS
I SHUTDOWN CRITICAL PARAMETERS PERFORMED IN MODES 5 AND 6 PORTRAYS PRESENT AND PROJECTED PLANT CONDITIONS TWO DAY LOOK-AHEAD PRESENTED TO MANAGEMENT FOR INTEGRATED ASSESSMENT OF SAFETY BARRIER PENETRATION INCLUDED IN THE WEEKLY OUTAGE REPORT TO FACILITATE OUTAGE PLANNING
MODE 5 AND 6 CRITICAL PARAMETERS FOR 02-11-1991 REACTOR COOLANT SYSTEM EM~Y DIESEL GENERAT~
SERVICE WATER PUMPS CCMPCNENT CCCllNG PUMPS Parameter (Acceptable Range)
RCS Inventory (42-120 in.):
Boration Flow Paths Available (0-4):
Charging Pumps Available {0-3):
Service Water Pumps Operable (2-4):
INVENTORY RHRPUMPS Ho.,.
74 in..
1 1
2340 ppm 2
1 3
1 BORATION A.ON PATH RCS B:FOJ Comments filled into PZR Alt. Charging Header 1-CH-P-1 A CHARGING-PUMPS 1-RH-P-1 A in service Emergency power source OOC Emergency* power source OOC 1 J Diesel Tagged STATUS OF CHANGES; RCS Inventory scheduled to be increased to 5% in the PZR.
PERSONNEL PERFORMANCE TRENDS TYPES OF PERSONNEL PERFORMANCE EVENTS CAUSAL FACTORS OF PERSONNEL
- PERFORMANCE EVENTS HPES PROGRAM COACHING PROGRAM
liWllill l,eiii*** &>co MODE 5 AND 6 CRITICAL PARAMETERS FOR 03-04-1991 REACTOR COOLANT SYSTEM EMER3B\\CY DIESEL GENERAT~
SERVICE WATER PUMPS.
CQ\\,1PO'JENT CCXl..JNG PUMPS Parameter (Acceptable Range)
RCS Inventory (42.:120 in.):
Boration Flow Paths Available (0-4):
Charging Pumps Available (0-3}:
Service Water Pumps Operable (2-4):
INVENTORY RHRPUMPS
~
120 in.
4 3
2388 ppm 2
2 4
2 BORATION A.DN PATH Comments CHARGING PUMPS 28% Cold Cal Pressurizer Level.
All paths available.
§TATUS OF CHANGES; Mode 4 entry is planned in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. No other changes are expected for the parameters descibed here in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
U)...
z w
w 20
~
10 a:
w m
- E
- , z 1 /89 2/89 MISPOSITION EVENTS 0
3/89 4/89 1/90 2/90 3/90 4/90 QUARTER / YEAR
U)
I-z w
w LL.
0 a:
w m
z 80 60 40 20 DOCUMENTS INCORRECTLY FOLLOWED 1 /89 2/89 3/89 4/89 1 /90 2/90 3/90 4/90 QUARTER / YEAR
40 30 0:
LU m 20
- E Z
10 0
1990 PERSONNEL ERRORS OPERATIONS AND MAINTENANCE First Second Third Fourth QUARTER II Operations IZI Maintenance
CAUSAL FACTORS FOR POTENTIALLY SIGNIFICANT PERSONNEL EVENTS SINCE 1988 MANAGERIAL METHODS 32°/o COMMUNICATIONS 26°/o MAN-MACHINE INTERFACE 12o/o WORK PRACTICES 11°/o
- TRAINING AND QUALIFICATION 4°/o
NORTH ANNA LER
SUMMARY
LERs BY SALP CATEGORY SINCE 8/31/90 8
6 6
4 4
2 0
0 0
OPS RAD.CNTL MAINT EP SECURITY ENG SAFETY
I I
I NORTH ANNA LERs BY NRC CATEGORY SINCE 8/31 /90 PERSONNEL ERRORS-OPERATING ACTIVITY ~
34%
OTHER (PROCEDURES) 13%
TOTAL LERs: 15
__/
DESIGN
~
13%
COMPONENT FAILURE 40%
12 10 8
6 4
2 0
NORTH ANNA INSPECTION REPORT
SUMMARY
WEAKNESSES SINCE 8/31/90 10 4
0 0
- RAD.CNTL MAINT EP SECURITY ENG SAFETY
- NORTH ANNA STRENGTHS SINCE 8/31/90 20 16 10 4
4 3
0 0
0 OPS RAD.CNTL MAINT EP SECURITY ENG SAFETY
SURRY NUCLEAR SAFETY ASSESSMENT.
J~ A. PRICE ASSISTANT STATION MANAGER -
NUCLEAR SAFETY AND LICENSING
SURRY NUCLEAR SAFETY ASSESSMENT PERFORMANCE ANNUNCIATORS AND TRENDS STATE OF NUCLEAR SAFETY
- PERFORMANCE ANNUNCIATORS AND TRENDS.
SURRY PERFORMANCE ANNUNCIATOR PANELS QUANTITATIVE EVALUATION CRITERIA TIGHTENING WINDOW COLOR SETPOINTS PANEL COLOR CHANGES SECOND, THIRD, AND FOURTH.
QUARTERS 1990 1990 PERFORMANCE ANNUNCIATOR TRENDS SIGNIFICANT WEAKNESS PANELS RED AND YELLOW PANEL CORRECTIVE ACTIONS
Surry Performance Annunciator Panel OPERATION MAINTENANCE PERFORMANCE PERSONNEL I
~----~-----~
EQUIPMENT PERFORMANCE PROGRAM PERFORMANCE PIANT EQUIVALENT AVAILAHIUTY FORCED OlITAGE RATE OPERATING PROGRAM REGULATORY PERFORMAN<-"E PROGRAM KEYSAFBTY RCS AND ISi FUEL SECONDARY SYSTISM PUMPAVALVE REUABIUTY SYSTEM PERFORMANCE
!ADVERSE TREND iNrEGRITY KEYSAIIETY THERMAL FSF SYSTBM PERFORMANCE ACTUATIONS AVAIIABIUTY
~NTENANCE PIANNINGA MODIFICATION SCHEDUUNG PROGRAM PROGRAM PROGRAM EMERGEN<:Y INDUSTRIAL SAFETY PREPAREDNE..C,S SAFETY MSESSMENT PROGRAM TRAINING PROGRAM HED YELLOW WIIITE l,HEEN PROGRAM ANDQUAUTY PROGRAM
- SIGNIFICANT WEAKNESS 0 - IMPROVEMENT NEEDED 0 - SATISFACTORY
- Sll,NIFICANT STHENC.TI I REACTOR TRIPS PROCl!DOD PROGRAM MATl!IUAIS PROGRAM.
EMERGENCY PREPAREDNESS EQUIPMENT AVAIIABIUTY CUP.MISTRY PERFORMANCE
- SfflS'*.
IINGINl!DING PIIOGMII
Surry Performance Annunciator Panel OPERATION Pl.ANT EQUIVALENT AVAII.ABIUTY FORCED OUTAl,E IU\\TE OPERA'nNG PROGIU\\M RADIATION PRO°i"EC'llON PROGIU\\M RE<.,l.11.ATOHY PEHFORMANCE MAJNTENANCE KEY SAFETY SYSTEM PERFORMAN E KEY SAFETY SYS. AVAILABILITY MAINTENANCE PROGRAM EMERGENCY PREPAREDNESS PROGRAM TRAINING PROGRAM*
PERSONNEL PERFORMANCE 2nd. 3rd & 4th Quarters. 1990 IU\\DIOLOGICAL NSS ENGINEERING PltOTECTION EQUIPMENT PERFORMANCE FUEL RCS I SECONDARY ISi
. EP EQUIPMENT RELIABILITY SYS INTEGRITY PUMP& VALVE AVAILABILITY ADVER E TREND TIIERMAI.
ESF REACTOR
- cHEMISTRY PERFORMANCE ACTUATIONS TRIPS PERFORMANCI!
PROGRAM PERFORMANCE Pl.ANNING &
MODIFIC..A 110N PROCEDURE Sl!CURITY SCHEDULING PROGRAM PROGRAM PROGRAM PROGRAM INDUSTRIAJ.
MATERIALS srrn SAFETY SAFETY ASSESS
~NGINEERING PROGRAM
/ QUALITY PROG PROGRAM PROGRAM HED
- SIGNIFICANT WEAKNESS
. YELLOW O - IMPROVEMENT NEEDED
- WIIITE O - SATISFACTORY GHEEN
- SIGNIFICANT STRENGTH
1990 SURRY WINDOWS TREND 250 247 226 200 189 150 100 83 88 50 41 Yi3{t:*
.*,**,*,*t,,,*,'
1fl!
5
,,;.;_:,:,:*:\\
3 60 0
2nd Quarter 3rd Quarter 4th Quarter
Surry Performance Annunciator Panel 1990 Fourth Quarter Significant Weakness Panels ENGINEERING KEY SAFETY SYSTEM KEY SAFETY SYSTEM MODIFICATION PERSONNEL PERFORMANCE:
PERFORMANCE:
PROGRAM:
PERFORMANCE:
UNIT 1 UNIT 2 PROJECT SIGNIFICANT EVENTS CLS CLS COORDINATION MODIACATION REGULATORY SITE ENGINEERING SITE ENGINEERING PROGRAM:
PERFORMANCE PROORAM PROGRAM PROORAM:
PERFORMANCE:
PERFORMANCE:
LE RS/SIGNIFICANT NRC STRENGTHS AND QUALITY OF DESIGN LERS EVENTS WEAKNESSES
- Surry Power Station Performance Annunciator Program.
VIRGINIA POWER 4th Quarter, 1990 -
Area Personnel Perlormance Panel Engineering Personnel Perlormance Area Number 1
- Panel Number 5 Window Numbe; IT] Signifjcant Events Criteria Green -
No significant events for the last 2 quarters.
White - No significant for the last quarter.
Yellow - 1 significant event in the last quarter.
Red - 2 of more significant events in the last quarter.
Justification
- 1. ESF actuations during testing.
- 2. LEA 90-019 - Feedwater transmitters found isolated during start-up.
- 3. Field change on head vent.
Management Corrective Actions
- 1) DETAILED ROOT CAUSE EVALUATION PERFORMED.
- 2) SUPERINTENDENT OF ENGINEERING REVIEWED THE EVENT WITH PERSONNEL
- INVOLVED.
- 3) "LESSONS LEARNED* MEMORANDUM DISTRIBUTED TO DESIGN, SYSTEM AND TESTING ENGINEERING PERSONNEL EMPHASIZING:
- USE OF CONTROWNG PROCEDURE WITH SIGNOFFS ANO qocUMENTATION.
- NEED TO CONSIDER SYSTEMS OPERATIONAL; IF NOT TAGGED OUT.
4)- SUADM-ENG-12 REVISED TO ENSURE NOTIFICATION OF THE SHIFT SUPERVISOR AND RETAGGING OF SYSTEM BOUNDARIES PRIOR TO 'NORK.
- 5) A TASK TEAM HAS BEEN FORMED TO INVESTIGATE THE STATION POLICIES ON PREJOB BRIEFS AND MAKE RECOMMENDATIONS FOR A COMMON POLICY NS APPROPRIATE.
March 14, 1991
STATE OF NUCLEAR SAFETY PAST PERFORMANCE IN KEY SAFETY AREAS RELATIVE TO INDUSTRY PERFORMANCE CURRENT PERFORMANCE IN KEY SAFETY AREAS RELATIVE TO PAST PERFORMANCE EVENTS WHICH COULD CHALLENGE OPERATORS AND PLANT REACTOR COOLANT SYSTEM AND STEAM GENERATOR INTEGRITY MATERIAL CONDITION OF KEY SAFETY SYSTEMS, SAFETY RELATED EQUIPMENT, AND EQUIPMENT IF NOT AVAILABLE HAS DIRECT IMPACT ON OPERATOR PRECURSORS OF SIGNIFICANT INDUSTRY ISSUES AND EVENTS PRECURSORS OF SIGNIFICANT PERSONNEL ERROR EVENTS
KEV SAFETY PER.FORMANCE PAST PERFORMANCE RELATIVE TO INDUSTRY PERFORMANCE CURRENT PERFORMANCE RELATIVE TO PAST PERFORMANCE
PERFORMANCE,INDICATORS FOR SURRY UNIT 2 PAST PERFORMANCE WORSE THAN AVERAGE BE1TER TitAN AVERAGE AUTO SCRAMS SCRAMS PER 1000 HRS EQUIVALENT AVAILABILITY FORCED OUTAGE RATE THERMAL PERFORMANCE (CANNOT BE CALCULATED 90-4)
CHEMISTRY INDEX FUEL RELABILITY SAFETY SYSTEM ACTUATIONS
-2
-1 0
1 2
(MEASURED IN STANDARD DEVIATIONS)
SPS DAT A BASED ON 4 QUARTER AVERAGE ENDING 90-4 INDUSTRY AVERAGE AND STANDARD DEVIATIONS ARE ESTIMATED FROM INPO DA TA
-2
-9.1S CURRENTPERFQRMANCE DECLINED IMPROVED NO SCRAMS IN 1990 ONE SSA DURINO 1llB4TII QUARTBR COMPARED 1U NONE IN nm PREVIOUS RJUR QUARTERS YIELDS AN INFINITY DOCLININO TR.END
-1 0
1 (MEASURED IN STANDARD OBVIATIONS)
DEVIATIONS OP LAST QUARTER FROM PREVIOUS 4 QUARTER A VERAGB (LAST QUARTER IS 90-4) 2
PERFORMANCE INDICATOR FOR SURRY (COMMON)
.* PAST PERFORMANCE WORSE THAN A VERA GE BEITER THAN AVERAGE
-0.76
-2
-1 0
1 2
(MEASURED IN STANDARD DEVIATIONS)
SPS DAT A BASED ON 4 QUARTER AVERAGE ENDING 90-4 INDUSTRY AVERAGE AND STANDARD DEVIATIONS ARE PSTIMATED FROM INPO DATA MA.INT BACKLOG > 3 MONTHS RATIO OF PM TO TOTAL MAINTENANCE PM ITEMS OVERDUE LOST TIME ACCIDENTS RADIATION EXPOSURE SKIN AND CLOTIUNG CONTAMINATION SOLID RADWASTE SHIPPED
-2 CURRENT PERFORMANCE DECLINED IMPROVED
-1 0
1 (MEASURED IN STANDARD Dl!VIATIONS)
DEVIATIONS OF LAST QUARTER FROM PREVIOUS 4 QUARTER MEANS (LAST QUARTER IS 90-4) 2
CHALLENGES TO PLANT OPERATIONS.
TRANSIENTS / TRIPS FORCED POWER REDUCTIONS REQUIRED SAFETY SYSTEM ACTUATIONS SAFETY SYSTEM ACTUATIONS DUE TO MAINTENANCE AND TEST ACTIVITIES SAFETY SYSTEM FAILURES *
- 1.
FORCED POWER REDUCTIONS AND TRANSIENTS UNITl 10 5
O 89-3 89-4 90-1 90-2 90-3 90-4 YEAR-QUARTER 0
UNIT2 20 10 0
89-3.
89-4 90-1 90-2 90-3 90-4 YEAR-QUARTER
3 2
1 0
REQUIRED SAFETY SYSTEM ACTUATIONS.
UNIT1 N
0 89-1 89-2 89-3 89-C t0-1 90-2 90-3 90-C YEAR-QUARTER N
3 _.I UNIT2 0
0 0
0 P4
- r.
0
tp: ;
89-1 89-2 8t-3,,_, to-1 to-2 to-3 to-c YEAR-QUARTER
5 -,I 4 -
fl) i 3-
~ 2-
~
0 -
1-0 0
0.,
H-1 H-2 ESF ACTUATIONS DUE TO TEST
& MAINTENANCE ACTIVITIES UNIT1 0
0 0
0 0
0 et-3 et-* to-1,0-2 to-3 to-*
YEAR/QUARTER r-UNIT2 5 _,,
4-I 3-
~ 2-
~
.-4 0
1-1r
,>-_0 __
0_. __
o __
o __
o __
o __ o-1 1jl\\
0 "
H-1 H-2. H-3 H-4 to-1 to-2 90-3 to-4 YEAR/QUARTER
4 SAFETY SYSTEM FAILURES UNIT1 N
N et-1 8'-2 H-3 H-4 to-1 90-2 90-3 90-4 YEAR-QUARTER 4
UNIT2 H-1 H-2 H-3 H-4 90-1 to-2 90-3 90-4 YEAR-QUARTER
MATERIAL CONDITION KEY SAFETY EQUIPMENT AVAILABILITY KEY SAFETY EQUIPMENT PERFORMANCE
- LONG TERM EQUIPMENT PROBLEM
- __ ---.* --. ---- __ J
SAFETY SYSTEM AVAILABILITY FOR SURRY UNIT 2 PAST PERFORMANCE WORSE THAN AVERAGE
- BE'ITER TIIAN AVERAGE
-2
-1 0
1 2
(MEASURED IN STANDARD DEVIATIONS)
SPS DAT A BASED ON 4 QUARTER AVERAGE ENDING 90-4 INDUSTRY AVERAGE AND STANDARD DEVIATIONS
. ARE ESTIMATED FROM JNPO DATA DG AVAILABILITY HHSI AVAILABILITY AFW AVAILABILITY
-2 CURRENT PERFORMANCE DECLINED
-1
~
~ 0.30
~
0 IMPROVED (MEASURED iN STANDARD DEVIATIONS)
DEVIATIONS OF LAST QUARTER FROM PREVIOUS 4 QUARTER MEANS (LAST QUARTER IS 90-4) 2
-2 SURRY UNIT 2 SAFETY SYSTEM PERFORMANCE LONG TERM PERFORMANCE WORSE THAN AVERAGE BE1TER fflAN AVERAGE
-1 0
. 1 (MEASURED IN STANDARD DEVIATIONS)
FROM 4/89 TO 9/90 2
SPRAY CONT ISOL VALVES SHORT TERM PERFORMANCE WORSE 'fHAN AVERAGE BETTER TIIAN AVERAGE
-2
-1 0
1 (MEASURED IN STANDARD DEVIATIONS)
FROM 4/90 TO 9/90 2
PRECURSOR EVENTS PRECURSORS OF SIGNIFICANT INDUSTRY ISSUES AND EVENTS PRECURSORS OF SIGNIFICANT PERSONNEL QA ERROR EVENTS
DR COMPARISON TO SELECTED SOERs 12 10 8
2 SOERS8-0l INSTRUMENT AIR SYSTEM FAILURES A VG:3.5/QTR 0..f-1,"'=.:.&,,.,i=~="""""'-'==~=~=~
89-3 89-4 90-1 90-2 90-3 90-4 SOER 82-10 FIRE BARRIER DEGRADATIONS 30 C'II N
20 A VG=S.66/QTR 10 0
89-3 89-4 90-1 90-2 90-3 90-4 30 20 10 12 10 B
6 4
SOER 83-09 VALVE INOPERABLITY CAUSED BY MOTOR OPERATOR FAILURES A VG:8.33/QTR 89-3
~9-4 90-1 90-2 90-3 90-4 SOERSS-02 VALVE MISPOSITIONING EVENTS INVOLVING HUMAN ERROR AVG=4.83/QTR 89-3 89-4 90-1 90-2 90-3 90-4
STATE OF QUALITY Re F. DRISCOLL MANAGER - CORPORATE QUALITY ASSURANCE
NORTH ANNA POWER STATION STATE OF QUALITY Fully 1 ---.---------------------------,
Acceptable Acceptable 2 Unsatisfactory 3 Unacceptable 4 -+--
Operations B Maintenance
- Radiological Protection
- Reassessment of areas previously rated greater than 2.0 or areas not previously assessed.
1.3
NORTH ANNA POWER STATION STATE OF*QUALITY MANAGEMENT INVOLVEMENT CRITICAL SELF ASSESSMENT PROGRAMS IMPROVING MAINTENANCE STRONG COMMITMENT TO SAFETY EFFECTIVE USE OF PERFORMANCE ASSESSMENTS CONTINUED MANAGEMENT ATTENTION NEEDED IN:
POST-MAINTENANCE TESTING USFAR UPDATE PROCEDURES CONSUMABLE MATERIAL CONTROLS
Fully 1
Acceptable Acceptable 2 Unsatisfactory 3 Unacceptable 4 SURRY POWER STATION STATE OF QUALITY Operations* m M~intenance
- Radiological Protection
- Reassessment of areas previously rated greater than 2.0 or areas not previously assessed.
1.3
SURRY POWER STATION STATE OF QUALITY STRONG SAFETY ATTITUDE MANAGEMENT INVOLVEMENT IMPROVING OPERATIONS STRONG COMMITMENT TO EMERGENCY PREPAREDNESS EFFECTIVE USE OF ASSESSMENTS CONTINUED MANAGEMENT ATTENTION NEEDED IN:
POST-MAINTENANCE TESTING UFSAR UPDATE PROCEDURES PLANNING FOREMAN INVOLVEMENT WITH WORK ACTIVITY
QUALITY ASSURANCE AUDIT AND ASSESSMENT PROGRAM ENHANCEMENTS ENGINEERING ASSESSMENTS PROGRAM HAS BEEN INITIATED 1991 ASSESSMENTS POST-MODIFICATION TESTING ENVIRONMENTAL QUALIFICATION INSERVICE TESTING COMPUTER SOFTWARE CONTROLS QA AUDIT PROGRAM HAS BEEN RESTRUCTURED QA AUDIT PROGRAM RESPONSIBILITY ASSIGNED TO MANAGER QUALITY ASSURANCE - CORPORATE.
ONE AUDIT TEAM COMPRISED OF SURRY, NORTH ANNA, AND CORPORATE PERSONEL CONDUCTS THE AUDIT AT ALL LOCATIONS MSRC REVIEW OF TECHNICAL SPECIFICATION REQUIRED AUDITS
QUALITY ASSURANCE AUDIT AND ASSESSMENT PROGRAM ENHANCEMENTS (continued)
ASSESSMENT PROGRAM ENHANCEMENTS INTEGRATION OF QUALITY ASSURANCE AND CORPORATE NUCLEAR SAFETY ASSESSMENT PLANS QA ASSESSMENTS PERFORMED AT SURRY, NORTH ANNA AND, CORPORATE BY SAME ASSESSMENT TEAM QA / CNS SHARING OF RESOURCES / EXPERTISE QUALITY ASSURANCE TRENDING PROGRAM BEING INITIATED INPUT FROM ALL QA GROUPS AUDITING PERFORMANCE SERVICES INSPECTION
- ANNUNCIATOR WINDOW REPORTING METHODOLOGY
QUALITY ASSURANCE ANNUNCIATOR WINDOWS FlJNCTI01' Al Allli'A~
bl Quarter, 1991 ENGINEERING OPERATIONS MAINTENANCE TECHNICAL SPECIFICATIONS I
2 J
4 LICENSING/
RECORDS RADIOLOGICAL SECURITY PROGRAMS ADMINISTRATION PROTECTION s
6 7
11 PROCUREMENT/
EMERGENCY FIRE MATERIAi.,
PREPAREDNESS PROTECTION CHEMISTRY CONTROL 9
10 II 12 INSERVICE SPECIAL NUCLEAR SITE CONFIGURATION INSPECTION PROCESSES SERVICES MANAGEMENT 1.l 14 IS 16 FITNESS NUCLEAR FOR PROCEDURES DUTY TRAINING 17 18 19 RED
- SIGNIFICANT WEAKNESS WHITE D -SATISFACTORY YELLOW D -IMPROVEMENT NEEDED GREEN
- STRENGTH
QUALITY ASSURANCE AUDIT AND ASSESSMENT PROGRAM ENHANCEMENTS (continued)
AUDIT/ ASSESSMENT RESOURCE IMPROVEMENTS TECHNICAL EXPERTISE PROVIDED BY CORPORATE NUCLEAR SAFETY VIRGINIA POWER / DUQUESNE LIGHT COMPANY AUDITOR EXCHANGE PROGRAM VIRGINIA POWER/ FLORIDA POWER CORPORATION TECHNICAL SPECIALIST EXCHANGE AGREEMENT INDUSTRY TECHNICAL SPECIALISTS COOPERATIVE MANAGEMENT AUDIT PROGRAM (CMAP)
MEMBER
. CONCLUDING REMARKS J.P. O'HANLON VICE PRESIDENT - NUCLEAR SERVICES
- ENCLOSURE 4 VIRGINIA POWER CONFIGURATION MANAGEMENT PROJECT UP.DATE MARCH 15, 1991
INTRODUCTION F. K. MOORE VICE PRESIDENT - ENGINEERING SERVICES
AGENDA STATUS OF SPECIFIC ACTIVITIES DOCUMENT ASSESSMENT DESIGN BASIS DOCUMENTATION PHYSICAL VERIFICATION VENDOR INFORMATION INFORMATION SYSTEMS ASSESSMENT BENEFITS IMPACT LESSONS LEARNED CONCLUSIONS
CONFIGURATION MANAGEMENT PROJECT UPDATE D. L. BENSON MANAGER-CONFIGURATION MANAGEMENT
DOCUMENT ASSESSMENT COLLECTION, REVIEW, AND INDEXING OF DOCUMENTS LIKELY TO CONTAIN DESIGN INFORMATION STATUS INITIAL DOCUMENT ASSESSMENT IS COMPLETE OVER 3,000,000 PAGES REVIEWED BATCH PROCESS UPDATING OF DOCUMENT DATA BASE WILL CONTINUE THROUGH 1991 INDEXING WILL BECOME "AUTOMATIC" AS SOON AS IMPROVED DOCUMENT MANAGEMENT SOFTWARE BECOMES OPERATIONAL
DESIGN BASIS DOCUMENTATION*
SCOPE PREPARATION OF APPROXIMATELY 60 SYSTEM DBDs AND ONE PLANT DBD PER SITE "INFORMATION ASSESSMENTS" EVALUATE MARGINS, CRITICAL CALCULATIONS, AND DESIGN DOCUMENTATION AND INITIATE ACTIONS TO CORRECT AREAS *oF WEAKN.ESS "DESIGN BASIS INTEGRATION REVIEWS" ARE PERFORMED
. TO CONFIRM PROPER INTEGRATION OF DESIGN BASIS INTO SYSTEM DESIGN, OPERATIONS, AND PRACTICES
SDBD SDBD SDBD SDBD SDBD Plant SDBD DESIGN BASIS DOCUMENT DEVELOPMENT SCHEDULE SURRY AND NORTH ANNA Group 1 Group 2 Group 3 Group 4 Group 5 DBD Group 6 1989 1990 1991 Draft Preparation 11111 Draft Review
- Information Assessment Draft Revision Issuance and Distribution
- -
- Current Status 1992 F-i*
mt_
DESIGN BASIS DOCUMENT GROUP IDENTIFICATION I
Group 1 Auxiliary Feedwater Service Water Instrument Air Emergency Power Diesel Generator D.C. Power Containment/Quench Spray Recirculation Spray Safety Injection Group 4 Nuclear Instrumentation.
Chemical and Volume Control Group 2 Component Cooling
- Main Steam Condensate Feedwater Station Service Power Group 5 Reactor Coolant Process Controls Group 3 Residual Heat Removal Reactor Protection Group 6 (Preliminary)
Auxiliary Decon Containment Fuel Building and Lab Area Ventilation
- Gaseous Waste,
Boron Recovery
DESIGN BASIS DOCUMENTATION (continued)
STATUS NINE DBDs ARE COMPLETE FOR EACH SITE AND ARE BEING PRINTED FOR DISTRIBUTION NINE "INFORMATION ASSESSMENTS" ARE
.COMPLETE FOR EACH SITE, RESULTING IN:
15 CALCULATIONS RECONSTITUTED 55 OPEN ITEMS 1800 DISCREPANCIES "DESIGN BASIS INTEGRATION REVIEWS" FOR FIRSf
- NINE SYSTEMS ARE BEING INITIATED FOR EACH SITE AND ARE SCHEDULED FOR COMPLETION.BY*
NOVEMBER 1991.
ELEVEN ADDITIONAL DBDs ARE IN PROGRESS FOR EACH SITE PLANT DBDs WILL BE INITIATED IN 1991 AND WILL BE COMPLETED BY DECEMBER 1992
PHYSICAL VERIFICATION WALKDOWNS.
SCOPE FUNCTIONAL VERIFICATION OF SYSTEM DESIGN AND COLLECTION OF DETAILED*COMPONENT DATA, DRAWING REVISION, AND COMPONENT LABELING STATUS SYSTEM WALKDOWN AND COMPONENT DATA COLLECTION SURRY - 45°/o COMPLETE NORTH ANNA - 55°/o COMPLETE COMPLETE BY MID-1992
PHYSICAL VERIFICATION WALKDOWNS
( continued)
STATUS (contintued).
COMPONENT LABELING AND DRAWING UPDATE SURRY - APPROXIMATELY 4°/o COMPLETE NORTH ANNA - APPROXIMATEL V 1°/o COMPLETE COMPLETE BY FIRST QUARTER 1993 FINDINGS NO MAJOR DISCREPANCIES HAVE BEEN IDENTIFIED NUMEROUS MINOR DRAWING DISCREPANCIES HAVE BEEN IDENTIFIED AND ARE BEING CORRECTED
VENDOR INFORMATION SCOPE ORGANIZATION AND UPDATING OF VENDOR INFORMATION CONSISTENT WITH INPO GUIDELINES
-, CONTROL OF VENDOR INFORMATION ASSIGNED TO ENGINEERING AT EACH SITE STATUS EXISTING VENDOR INFORMATION INDEXED APPROXIMATELY 2°/o OF MANUALS UPGRADED ENGINEERING WILL ASSUME CONTROL OF UPGRADED VENDOR INFORMATION BY JUNE 1991 UPGRADE OF VENDOR MANUALS TO BE COMPLETE BY MID-1993
INFORMATION SYSTEMS NEW INFORMATION SYSTEMS BEING DEVELOPED DMIS-"DOCUMENT INDEXING AND CHANGE STATUS SYSTEM EDS - MASTER LIST OF COMPONENT INFORMATION BOM - PARTS INFORMATION FOR INSTALLED COMPONENTS STATUS DMIS - RECORDS MANAGEMENT FUNCTIONS COMPLETE
- CONFIGURATION CHANGE STATUS AND INDEX FEATURES TO BE OPERATIONAL BY END OF 1991 EDS-TO BE COMPLETE BY JUNE 1991 BOM-TO BE COMPLETE BY DECEMBER 1991
ASSESSMENT - BENEFITS, IMPACT, AND LESSONS LEARNED PROJECT ACTIVITIES HAVE INCREASED "DESIGN BASIS AWARENESS" AND HAVE RESULTED IN IMPROVEMENTS IN SYSTEM PE*RFORMANCE DOCUMENT ASSESSMENT HAS INCREASED AVAILABLITY AND RETRIEVABILITY OF DESIGN INFORMATION AND WILL HAVE BENEFITS FAR.
BEYOND THIS PROJECT DESIGN BASIS DOCUMENTATION - OUR EMPHASIS ON REFERENCE TRACEABILITY AND COMPONENT LEVEL INFORMATION IS THE CORRECT APPROACH NO MAJOR SYSTEM OPERABILITY CONCERNS HAVE
- BEEN IDENTIFIED IN OUR REVIEWS TO DATE INITIAL PRODUCTION OF 18 SYSTEM DBD DRAFTS IN 1989 STRAINED OUR RESOURCES AND ARCHITECT/ENGINEER RESOURCES PHYSICAL VERIFICATION AND VENDOR INFORMATION WORK HAS GONE WELL AND IS STEADILY IMPROVING QUALITY OF EQUIPMENT DATA
CONCLUSIONS PROJECT HAS PROCEEDED AS PLANNED WITH ONL V MINOR CHANGES TO SCOPE AND
.SCHEDULE INITIAL RECEPTION OF PRODUCTS HAS BEEN VERY POSITIVE PROJECT HAS BEEN AND CONTINUES TO BE EFFECTIVE IN:
UPGRADING DESIGN BASIS INFORMATION IMPROVING OUR ABILITY TO PROVIDE ENGINEERING SERVICES AND ENHANCE SYSTEM PERFORMANCE SUPPORTING OTHER ACTIVITIIES AND PROGRAMS
,,...'6 r) *
~ - -
Sources System Records S&W Westinghouse Vendors NRC/PDR Component Walkdown Data Vendors Records CONFIGURATION MANAGEMENT PROJECT Project Activities I
Information Corrective I
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Assessment Actions
, I I
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~ Document I
DBD Preparation Assessment I
I I
I Documents I..
Records
~
I r Management I
Upgrade I
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I Inf ormalion DMIS
~
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System EDS I..
Development BOM ----
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Data LL I
Collection BOM I
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System I
Development I
Document -
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Review I
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I Information I
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Relabeling, I
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Drawing I
I Revision I
Products tr@
OBDs Records-Station Corporate
/
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IBM DMIS EDS BOM
~
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Drawing Chan ges, eling Improved Lab
~------------------------------+---------
I Current I
Improved Configuration Processes I
Control Procedures Analysis of Recommend and Implement I
Existing Process Changes I
I Processes I r I
Users
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