ML17285A325

Summary of 890131 Meeting W/Util in Rockville,Md Re Improvement of Safety Performance at Plant.Viewgraphs Encl

ML17285A325
Person / Time
Site:	Columbia
Issue date:	02/27/1989
From:	Samworth R Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8903200261
Download: ML17285A325 (56)

Text

February 27, 1989 Docket No.

397 LICENSEE:

FAGILITY

'UBJECT'E:

Washington Public Power Supply System Washington Nuclear Project No.

2

SUMMARY

OF MEETING HELD OtJ JANUARY 31, 1989 IMPROVEMENT OF SAFETY. PERFORMANCE AT WNP-2 On January 31, 1989, Washington Public Power Supply System (WPPSS) officials met with NRC management representatives to discuss initiatives to improve safety performance at WNP-2.

Attendees were:

NRC G. Holahan M. Virgilio G. Knighton l<PPS Donald W. Mazur Gary D. Bouchey Gerald C. Sorensen The printed outline (copy enclosed) followed by the WPPSS officials in their presentation provides a

summary of subjects discussed at the meeting.

Robert B. Samworth, Project Manager Project Directorate V

Division of Reactor Projects - III, IV, V and Special Projects

Enclosure:

As stated cc w/enclosure:

See next page DISTRIBUTION NRC JI Local PDRs JSniezek PDV Reading GKnighton RSamworth OGC f

EJordan BGrimes NRC Participants ACRS (10)

MJohnson, RV LWPPS MTG

SUMMARY

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J.I; 4~**4 UNITED STATES CLEAR REGULATORY COMMISSIO WASHINGTON, D. C. 20555 February 27, 1989 Docket

>to.

397 LICENSEE:

FACILITY

'UBJECT:

RE:

ltashington Public Power Supply System Washington Nuclear Project No.

2

SUMMARY

OF MEETING HELD OH JANUARY 31, 1989 IMPROVEtIENT OF SAFETY PERFORMANCE AT Wti'P-2 On January 31,

1989, Washirigton Public Power Supply System (ltPPSS) officials met with NRC management representatives to discuss initiatives to improve safety performance at WNP-2.

Attendees were:

NRC G. Holahan t~. Virgilio G.'nightoni WPPS Donald W. Mazur Gary D. Bouchey Gerald C.

Sorensen The printed'outline (copy enclosed) followed by the IIPPSS officials in their presentation provides-a summary of subjects discussed at the meeting.

Robert B. Samworth, Project Manager Project Directorate V

Division of Reactor Projects

- III, IV, V and Special Projects

Enclosure:

As stated cc w/enclosure:

See next page

P

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Nr.

G.

C. Sorensen, Manager

'Washington Public Power Supply System WPPSS Nuclear Project No.

2 (WNP-2)

CC:

Ni cholas S.

Reynolds, Esq.

Bishop, Cook, Purcell 5 Reynolds 1400 L Street NW Washington, D.C.

20005-3502 Mr. G.

E. Doupe, Esquire Washington Public Power Supply System P. 0.

Box 968 3000 George Washington Way Richland, Washington 99532 Nr. Curti s Esche ls, Chai rman Energy Facility Site Evaluation Council Nail Stop PY-ll Olympia, Washington 98504 Nr. Alan G. Hosier, Licensing Na>>ager Washington Public Power Supply System P.

0.

Box 968, VD 956B

Richland, Hashing tun 99352 Hr. A. Lee Oxsen Ass'istant Managing Director for Operations Washington Public Power Supply System P.

0.

Box 968, ND 1023

Richland, WA 99352 h1r.

Gary D. Bouchey, Director Licensing and Assurance Washington Public Power Supply System P.

O.

Box 968, ND 280

Richland, Washington 99352 Nr.

C.

M. Powers WNP-2 Plant Manager Washington Public Power Supply System P. 0.

Box HD 927M

Richland, Washington 99352 Regional Administrator, Region V

U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Chairman Benton County Board of Commissioners

Prosser, Washington 99350 Nr. Christian Bosted U. S. Nuclear Regulatory Commission P.

0.

Box 69

Richland, Washington 99352

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k SUPPLY SYSTEM NRC HEADQUARTERS ROCKVXLLEt MARYLAND JANUARY 31, 1989 WASHINGTON PUBLIC POWER 4N SUPPLY SYSTEM

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e.

OVERALL PLANT PERFORMANCE o

Successful

'Refueling Outage (R-3) /So 1 i d Recovery o

Four (4)

Forced Outages to Cold Shutdown High Drywell Leakage (RCIC Steam Supply, Valve Packing)

Nain Steam Line Drain Cracked Weld CSP-V-9 Seat Leakage Condenser Tube Leak o

Generation Higher Than Budgeted o

Personnel Performance Improved o

Nanagement Initiatives Paying Dividends Personnel Accountability/Procedural Compliance Nanagement Involvement/Problem Resolution Root Cause Analysis and Plant Problem Process o

Selected Performance Indicators

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1 STRATEGIC PLAN FOR THE SUPPLY SYSTEM

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Effort Began for the First Time in August 1987

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Planning Completed in September 1988

Reviews, Approval and Printing Complete in December 1988 e

Purpose Define the Intended Future Through 1995 Express the Vision and Action to Reach It

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Points of Emphasis A Statement of Values, Shared by Employees Highest Priority to Safe,

Reliable, Economic Operation of Plant 2

Commitment to Improved Plant and Employee Performance

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MANAGEMEhTRAINING IN THE SUPP SYSTEM

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An Old Subject

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New Commitments Flowing from Strategic Plan and Concerns Expressed by INPO and NRC

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Management and Personnel Manual Issued November 14 o

Thrust of Program Assurance of Acceptable Level of Skills Stimulate a

New Culture of Participative Management and Employee Involvement Methods and Stimulus to Practice Teamwork Leading to an Inner-Driven Accountability for Work e

Highlights Management Development Track Established Covers All Managers and Supervisors Established Mandatory Training Required Core - For All Levels of Management Required Varies by Level of Position Elective To Suit Job and Individual Needs Action Plans will Become a Contract

\\

o Old Process Offered Some of the Right Training to Some Managers New Process is Comprehensive, with Purpose and "Teeth" e

From November Through January, Managers are Being Trained in Quality Management Skills e

Not a One-Shot or a

One Year Program A Long-Term Process of Continuous Improvement

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SUPPLY SYSTEM SSFI CHRONOLOGY

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NRC Performed SSFI at WNP-2 e

NRC Commitment to Perform SSFI

.e LPCS Draft Design Bases Document Completed August 1987 January 1988 July 1988

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e SSFI Program Manual Issued August 1988 e

Team for Inspection of Low Pressure Core

'ugust 1988 Spray (LPCS)

System Selected e

LPCS Inspection Initiated e

LPCS Inspection Report Issued e

Tracking and Evaluation of Open Items Resolution by Engineering Assurance e

Perform 1

SSFI August 1988 December 1988 Ongoing FY 90

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SAFETY SYSTEM FUNCTIONAL INSPECTION (SSFI)

OBJECTIVES:

e Perform pilot self-initiated inspection similar in approach and thoroughness to NRC SSFIs

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Assess operational readiness of the Low Pressure Core Spray (LPCS)

System e

Use technical personnel that have been reasonably free from involvement in LPCS system design, modification,

testing, maintenance and operation.

e Provide feedback to assist in validation of the Design Bases Document (DBD) e Develop experience for planning future SSFIs

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LPCS INSPECTION RESULTS

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183 Observations 5 Good Practices 34 Design Bases Document 144 System Related 16 NCRs Initiated

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Concerns and Areas for Improvement were Identified

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Number of Observations are Programmatic in Nature e

Approximately 50K of Observations Involve Procedures and Configuration Control Issues e

Many Observations are Duplicate/Similar to Those Previously Identified

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INSPECTION CONCLUSIONS o

LPCS System Mill Perform Its Intended Design Function e

Methodology outlined in 'SSFI Program Manual is sound, we have confidence in our approach,

process, and results.

e Structured DBD Verification is Necessary a

DBD is Valuable Source Reference e

Programmatic, Procedures, and Configuration Control Observations Collectively Represent an Area of Concern not Limited to LPCS o

Plant Staff Participation Extremely Valuable

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INSPECTION RECOMMENDATIONS

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Develop a Plan to Address Disposition of Observations e

Integrate Observations Disposition Into Current Improvement Programs

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Apply Root Cause Analysis for Identification of Root Problem e

Commit Full-time Participant from Plant Technical Staff for Future SSFIs o

Do Not Perform SSFIs During Refueling Outages

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HEALTH PHYSICS PERFORMANCE ASSESSMENTS e

Rigorous Examination of CY88 Radiological Occurrence Reports (RORs)

Determine Root Causes Describe Trends Framework for Improvement Action Plan o

Results Poor Radiological Work Practices Failure to Adhere to HP Controls e

Planned Actions Enhance Radiological Training Disciplinary Action Policy ROR Program Improvements Revise Radiation Work Permit Procedure Additional HP Personnel All Craft Supervisors Nanagement and Supervisory Field Tours Training Video on Individual Responsibility

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Attachment 3

Page 1 of 3

'4 Equivalent Availability Faator 598 gl9 gls 6IS 60,7 6L3 613 20 10 NN INI IN2 INS IS%

INS INi IN7 INi 1990 prof,.

goal Unplanned Automatic Scrams While Critical v 5 h.

b3 7A INO INI IN2 ISQ jNi, ISN INi 1987 ISQ 1990 pro(e goal Cross Heat Rate 11000 P 'IOSOO

> IOOOO e

W 9500

~ 10,444 10 10/11 10v315 10~ Igg I(@60 INN INI

'IN2 ISQ INi IN$

INi IN7 INI

'990 pro f.

goal Projectec 1988. values are based on data through Qe-tember

1988, except that the auto"vatic scram value is based or. data throuch Decembe 15, 19SS.

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Attachment 3

Page 2 of 3 Collective Radiation Exposure BWR Average 1200 1000

,061 1,017 1,137 1

5?1 451 IM0 INI IN2 IM3 IS54 IM5 IN5 I$57 IN5 ISM pro].

goal Collective Radiation Exposure PWR Average 707 591 M5 g 500 h.

C 400 P

aRN 397 IM0 INI IN2 ISQ IN4 IM5 1$55 IM7 IN5 IS SO pro],

goal Volume of Lo&ivel Solid Radioactive Waste BWR Average 1200 C

500 h.

3 500 E

400 1,1 13 493 45$

IM0 IS51

'IN2 19M 1$54 IS5$

IS54 IM7 IS55 pro]a ISSO goal Projected 1988 values are oasec on aata through Seotenber 1988.

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Attachment 3

Page 3 of 3 Volume of Lo&evel Solid Radioactive Waste PWR Average

> 400 k 300 le E

~ 200 Pe 211 2I3 19M N1 1992 1999 1%i N5 1999 ISED 19M prof.

1990 goal fadaefriaf Safely Lost-Time Accident Rate 1 40

~ lM

~ 120 1,10 h1.00 g 0.90

~E 0.60 I

0.70

.0.50 g 0.50

~ 0.40

~ 030 E 0,20 e: 0.10 0

I26 L66 'g 0,71 OA 0.19 NO 1991 19@

199 195i IM5 19f%

MT 19M 1990 proIa gool Projected 1988 values are based on data through Seotember

'988.

110%

UNIT EQUIVALENT AVAILABILITYFACTOR

>vNP-2 100%

90%

00%

70%

60%

40%

30%

20%

10%

+

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F hf A

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CY 1900

(;X'909 0

CURRENT MONTII 1987 IND AVG

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10.280 PLANT THERMAL PERFORMANCF WNP-?

10.270 10.260 10.250 10.24 0 E"

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Qg IK CI L~

10.230 10 220-10.210 10.200

10. 190 10.180 10.170 10.160 10.150 J

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SUPPLY SYSTEM FY89 GOAL J

F hI A

hf J

J A

S 0

N D

CY 1988 0

COhihiERCIAL J

F hf A

M J

J A

S 0

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CY 1989 FY 1989 GOAL

UNPLANNED SCRAMS

%NP-2 J

F hf A

hf J

J A

S 0

N D

J F

hf A

hf J

J A

S 0

N D

G YTD CY 1968 C URRENT hf0 N'I'H CY 1969 1967 IND AVG

t l

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1.500 1.4.00 1.300 1.200

1. 100 1.000 0.900 VN 0.800 O

0.700 bl Q

0600 Pi 0.500 0.-1 00 0.300 0.200 0.100 0.000 SCRAMS PFR '1000 HOURS CRITICAL WNP-2 J

F hf A

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GY 1900 l3 YEAR TO DATE J

F M

A ht J

J A

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N' GY 1989 TARGET

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UNPLANNED SAFFTY SYSTEM ACTUATIDNS 00 00 00 00 00 00 00 00 00 00 00 00 0

J F

hf A

hl J

J A

S 0

N D

CY 1988 AC P-OW'ER J

F M

A hi J

J A

S 0

N D

CY 1989 ECCS

170 160 150 MONTHLY EXPOSURE WNP-2 129.7 120 110 100-90 80 70 60 5

40 30 24.5

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/g 62.7 23 g4.6 20 6 9.8

14. 8 18.1

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CY 1988 CURRENT MONTH CY 1989

P P

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'300 YEAR-TO-DATE EXPOSURE WNE'-2 800 700 600 500 400 300 happ 100 ~~~~~~

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T T

T J

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hf J

J A

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N 9

J F

hf A

hf J

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CY 1 908 CY 1989 0

YEAP. TO DATE 1987 1ND AUG

20 19 18 17 16 15 RADIOACTIVFWASTF.. SHIPPED OFF SITF WNP-2 10 J

F hf A

hf J

J A

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N D

J F

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M J

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0 YTD CY 1908 CURRENT MONTH CY 1989 1987 IND AVG

Kf R Xe OFF-GAS RELEASE RATE 1VNP-2 4287 3399 2 5 194 1.5 0.5 J

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cr

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27 2Q 39 55 53 LQZ15~

hi J

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J F

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hi J

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CY 1900

)r'.-~'j CUkRENT MONT(i K

CY 1989

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100 QA SURVFILLANCE DEFICIENCIFS 1VNP 2 60 70 60 50 40 30 10 0 M I

J F

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CY 1900 NET

~mr' LOS ED J

F M

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D CY 1989

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P.EMAI NING

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5.50 LOST TIME ACCIDENT RATE WNP-2 5.00

'4 50 4.00 3 50 3.00 2.50 2 00 1 50 1.00 0 50 0.00 l~ 'T ~l J

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A M

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CY 1988 GY 1989 LI WNP-2 ACCIDENT RATE 1987 IND AVG

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LICENSE AMENDMENTS NEEDED - R-4 W

o Reload A

o March 1989 o

Includes 4

Lead Test Assemblies of 9 X 9 Design o

License Condition 2.C(16), Att. 2, Item 3(b)

Wide Range Neutron Monitor

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4

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R4 OUTAGE SCOPE MAJOR DESIGN CHANGE/MAINTENANCE TASKS

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SM 75/85 Logi c

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SW A/B Discharge X Hi e

Leak Detection Instrument Replacement

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0/W Hot Spot Removal e

RHR 53A Valve Replacement o

Feedwater Heater Level Control Change-Out e

IN-1 Inverter Replacement

~

Turbine Supervisory Instrument Replacement

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MSIY Overhaul e

RFW Turbine Inspection e

Turbine Valve Overhaul o

MSRV Actuator Rebuild e

MSRV Replacement/Seat Rework e

Acoustical Monitor Cable Replacement o

CRD Rebuild

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RRC Discharge Valve Inspection/Modification o

MS SRV Vacuum Breaker Rework

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II MNP-2 SIMULATOR o

Deci si on to Repl ace Exi sting Simul ator o

Contract Awarded to Westinghouse December 16, 1988 Contract Schedule o

30 Months from Notice to Proceed to Acceptance o

Misses 10CFR55.45 Date Certification Due (March 1991) o Existing Simulator Will be Used in Interim Special Consideration for Shortcomings

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CORE DESIGN RELOAD ANALYSIS DEVELOPMENT MILESTONES 6/86 Program budget and goals approved 11/86 Consulting contracts executed with YAEC 6/87 All major computer codes are operational 9/87 First recommended reload pattern transmitted to fuel vendor 10/87 6/88 9/88 Initiated computer code and model benchmarking (Quad Ci,ties, Peach

Bottom, and WNP-2)

Engineering and design procedures have been issued Second recommended reload pattern transmitted to fuel vendor 6/89 Major computer codes to be verified and validated 9/89 Third recommended reload pattern to be transmitted to fuel vendor 12/89 3/91 6/91 Topical submittals to begin o

BWR Core Physics Methods (12/89) o BWR Transient Methods (6/90) o Applications Methodology Online Core moni toring (12/90)

First Supply System reload license submittal License amendment issued by NRC The Supply System will update the NRC in late March 1989 regarding the status of our schedule to submit the topicals for review beginning in December 1989.

MNP-1/3 PRESERVATION PLAN WNP-1 o

In Preservation Since 1982 o

Budget

$ 5. 0 Mil 1 i on Per Year Achieved Minimum Preservation Level August 1988 WNP-3 o

In Preservation Since 1983 o

Budget

$ 5.5 Million Per Year o

Achieved Minimum Preservation Level August 1988 o

Attempting to Close Geology Review o

NRC Review effort/SER needed'o document status of review o

Staff review to date has produced no adverse comments on method,

data, or conclusions

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