ML20046C822

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Summary of 930618 Public Meeting W/Valve Technical Resolution Group of BWR Owners Group Re MOV Issues.List of Attendees,Meeting Agenda & Presentation Handout Encl
ML20046C822
Person / Time
Issue date: 06/22/1993
From: Sullivan E
Office of Nuclear Reactor Regulation
To: Norberg J
Office of Nuclear Reactor Regulation
References
NUDOCS 9308120236
Download: ML20046C822 (23)


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WASHINGTON, D.C.F Yo MEMORANDUM FOR: James A. Norberg, Chief Mechanical Engineering Branch FROM:

Edmund J. Sullivan, Jr., Chief Pumps and Valves Sectio.:

Mechanical Engineering Branch

SUBJECT:

MINUTES OF PUBLIC MEETING BETWEEN THE NRC STAFF AND THE VALVE TECHNICAL RESOLUTION GROUP OF THE BWR OWNERS' GROUP On June 18, 1993, members of the NRC staff held a public meeting with the Valve Technical Resolution Group of the Boiling Water Reactor Owners' Group (BWROG) to discuss motor-operated valve (MOV) issues.

Enclosed are (1) the attendance list from the meeting, (2) the meeting agenda, (3) the BWROG presentation handout, and (4) the NRC staff presentation handout.

The BWROG described its current activities to assist BWR nuclear power plant licensees in improving the performance of MOVs and implementing programs in response to Generic letter (GL) 89-10, " Safety-Related Motor-0perated Valve Testing and Surveillance." The BWROG concluded that the establishment of MOV programs in response to GL 89-10 had been warranted in light of the improved understanding of M0V design basis, improved control of MOV switch settings, improved MOV diagnostics and trending, improved in-house MOV expertise among licensees, improved MOV maintenance and reliability, and correction of numerous MOV problems.

The'BWROG stated that, because the activities in response to GL 89-10 were reaching the point of diminishing returns, new issues (such as the recent Limitorque Part 21 notification on ac motor temperature effects) should be addressed outside the GL 89-10 program. Over the long term, the BWROG stated that the GL 89-10 activities should be incorporated into a maintenance program to ensure continued MOV capability.

The staff provided a qummary of its activities to monitor licensee efforts to improve the performance of MOVs in nuclear power plants.

For' example, the staff discussed Revision 1 (June 14, 1993) to Temporary Instruction 2515/109,

" Inspection Requirements for Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance." TLe staff agreed that, after completing the five-year testing program to verify the design-basis capability of safety-related.MOVs, licensees could implement the long-term aspects of GL 89-10 to periodically verify MOV design-basis capability through MOV maintenance prograas. With respect to new issues (such as ac motor temperature offeds), the staff stated that licensees need to determine whether the new information can cause operability problems.

However, licensees are not required to re-perform all M0V design-basis reviews and calculations to incorporate new information if sufficient margin exists to demonstrate that an operability concern is not present.

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The BWROG stated that licensees are concerned that the NRC staff places excessive emphasis on M0V issues by categorizing them as inspector followup items during GL 89-10 inspections. The staff stated that categorizing an issue as an inspector-followup item ensures that the staff reviews licensee actions to address the issue. A licensee should not consider an issue to be highest priority solely on the basis of its categorization as an inspector followup item.

The BWROG stated that the Electric Power Research Institute (EPRI) might not provide sufficient information to allow licensees to setup nontestable MOVs before the GL 89-10 schedule date of June 28, 1994. The staff stated that licensees should discuss the prompt release of summarized M0V test information with EPRI to help licensees meet their GL 89-10 schedule commitments.

If EPRI data are not available, licensees might need to use best available MOV test data from other sources.

The BWROG stated that an MOV test database might not be reliable because of the differences between apparently identical MOVs.

The staff believes that licensees will need to share MOV test data in order to size and set M0Vs that cannot be dynamically tested in a timely manner. The staff continues to encourage licensees to establish an M0V test database.

The staff considered the meeting with the BWROG to have been successful in exchanging information and ideas on resolving concerns about MOV performance in a timely manner.

g4fd Aw v.._ w BY; Edmund J. Sullivan, Jr., Chief Pumps and Valves Section Mechanical Engineering Branch

Enclosures:

As stated Distribution:

Central / Files; NRC PDR EMEB RF/CHRON TScarbrough Valve Distribution List (w/o enclosures)

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Topic VALVE TRG-NRC MEETING RE MOV Date JUNE 18, 1993 Location ROCKVILLE, MD (NRC 0FFICES)

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Topic VALVE TRG-NRC MEETING RE MOV Date JUNE 18, 1993 Location ROCKVILLE, MD (NRC 0FFICES)

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s Ene losae 1 AGENDA FOR PUBLIC MEETING BETWEEN NRC STAFF AND VALVE TRG COMMITTEE OF THE BOILING WATER REACTOR OWNERS' GROUP JUNE 18, 1993 ONE WHITE FLINT NORTH ROOM 1F7/9 9:00 AM INTRODUCTIONS AND OPENING REMARKS D. ATWOOD (BWROG)

T. SCARBROUGH (NRC) 9:30 AM DISCUSSIONS OF MOV ITEMS OF INTEREST 1.

NRC STAFF POSITION ON THE DEVELOPMENT OF PROBABILISTIC AND/OR PERFORMANCE-BASED METHODOLOGIES, "THE GRADED APPROACH," TO CHARACTERIZE AN MOV'S SAFETY SIGNIFICANCE.

I 2.

USE OF "THE GRADED APPROACH" FOR TESTING AND VERIFICATION OF DESIGN ADEQUACY OF GL 89-10 MOVS.

3.

REVISION 1 0F TI 2515/109 AND THE TECHNICAL CRITERIA TO BE USED DURING PART 2 INSPECTIONS.

4.

NRC SCHEDULE-FOR REVIEWING EPRI RESULTS AND PREPARATION 10F SER.

5.

NRC STAFF'S VIEWS ON INDUSTRY MOV DATABASE SUCH AS ITS VALUE AND USE.

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EXTRAPOLATION OF DIFFERENTIAL PRESSURE TEST DATA.

7.

STATUS OF ANTICIPATED SUPPLEMENTS TO-GL 89-10.

8.

STATUS OF PREPARATION OF TEST-ACCEPTANCE CRITERIA BY BWROG.

9.

COORDINATION OF ACTIVITIES OF DIFFERENT BWROG COMMITTEES IN MOV AREAS, SUCH AS:

THE-USE OF-PRA STUDIES.

11:30 AM CLOSING REMARKS i

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COMMITTEE OVERVIEW o

FORMED:

1991 o

MEMBERSHIP: ALL 22 DOMESTIC BWROG UTILITIES o

OBJECTIVE:

GENERICALLY ADDRESS GL 89-10 BWR ISSUES INTERRELATIONSHIPS o

MUG o

NUMARC TECHNICAL ADVISORY GROUPS AD H0C ADVISORY COMMITTEES o

EPRI PERFORMANCE PREDICTION PROGRAM o

LIMITORQUE o

KALSI ENGINEERING, INC.

o BWROG INTEGRATED RISK-BASED REGULATION COMMITTEE (PRA-MOV) o NRC t

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COMPLETED COMMITTEE WORK o

TRENDING GUIDELINES o

VOLTAGE DROP CALCULATIONS / THERMAL OVERLOAD SIZING CRITERIA o

SUMMARY

OF RATE OF LOADING ISSUES o

oP TESTING ACCEPTANCE CRITERIA o

LIMITORQUE LIMITER PLATE POSITION PAPER o

MOV GROUPING CRITERIA o

INFORMATION EXCHANGE WGF23/061893

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UTILITY ACTIONS NEEDED TO ACHIEVE GL 89-10 OBJECTIVES o

DESIGN BASIS REVIEWS CONFIRM DESIGN BASIS CONDITIONS CONFIRM SAFETY FUNCTION o

SIZING CALCULATIONS CONSIDER DEGRADED VOLTAGE CONFIRM ACTUATOR SIZING CONFIRM STRUCTURAL ADEQUACY PERFORM WINDOW CALCULATIONS USE REASONABLE DESIGN VALUES FOR UNCERTAINTIES (E.G. VALVE FACTOR, STEM FRICTION FACTOR, ROL) o BASELINE STATIC TEST TEST AND SET-UP PROCEDURES IN PLACE CONTROL OF SWITCH SETTINGS ESTABLISHED DIAGNOSTIC EQUIPMENT ACCURACY CORRECTLY APPLIED o

FLOW TEST (REASONABLE ALTERNATIVES TO "ALL VALVES PRACTICABLE")

DEFINE VALVE GROUPS AND TEST REPRESENTATIVE SAMPLE; EXTEND RESULTS TO UNTESTED MOVs BY EPRI METHOD OR OTHER REASONABLE APPROACH USE EPRI EMPIRICAL EQUATION oP TEST WAIVED FOR MOVs WITH LARGE MARGIN WGF23/061893

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UTILITY ACTIONS NEEDED TO ACHIEVE GL 89-10 OBJECTIVES (CONTINUED) i 1

o DESIGN CHANGES COMPARE FLOW TEST RESULTS TO SPECIFICATION

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REQUIREMENTS JUSTIFYLOPERABILITY_0R PERFORM DESIGN CHANGESLIFE SPECIFICALLY NOT~ CONSERVATIVE o

PERFORMANCE VERIFICATION I

USE PRA PRIORITIZATION METHODOLOGY FOR MOV RANKING-DETERMINE RETEST' FREQUENCY CONSIDERING SUCH THINGS.

AS IMPORTANCE,-MAINTENANCE EXPERIENCE,_ FEMA, RCH WAIVE RETEST FOR "NON-SAFETY.SIGNIFICANT" MOVs-CONDUCT FUTURE RETESTING UNDER STATIC CONDITIONS s

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AGENDA FOR PUBLIC MEETING BETWEEN NRC STAFF AND VALVE TRG COMMITTEE OF THE BOILING WATER REACTOR OWNERS' GROUP JUNE 18, 1993 ONE WNITE FLINT NORTH ROOM 1F7/9 9:00 AM INTRODUCTIONS AND OPENING REMARKS D. ATw0OD (BWROG) a T. SCARBROUGH (NRC) j 9:30 AM DISCUSSIONS.0F MOV ITEMS OF INTEREST 1

1.

NRC STAFF POSITION ON THE DEVELOPMENT OF PROBABILISTIC AND/OR. PERFORMANCE-BASED METHODOLOGIES, "THE GRADED-APPROACH," TO CHARACTERIZE AN MOV'S SAFETY SIGNIFICANCE.

2.

USE'OF "THE GRADED APPROACH" FOR TESTING AND VERIFICATION OF DESIGN ADEQUACY OF GL 89-10 MOVS.

3.

REVISION 1 0F TI 2515/109 AND-THE-TECHNICAL CRITERIA TO BE USED DURING-PART 2 INSPECTIONS.

4.

NRC-SCHEDULE FOR REVIEWING EPRI RESULTS AND PREPARATION OF SER.

5.

NRC STAFF'S VIEWS ON. INDUSTRY MOV DATABASE SUCH AS ITS'VALUE AND USE.

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6.

EXTRAPOLATION OF DIFFERENTIAL PRESSURE TEST DATA.

7.

STATUS OF ANTICIPATED SUPPLEMENTS TO GL 89-10.

8.

STATUS OF PREPARATION OF TEST ACCEPTANCE CRITERIA BY BWROG.

9.

COORDINATION OF ACTIVITIES OF DIFFERENT BWROG COMITTEES IN MOV AREAS, SUCH AS THE USE OF PRA STUDIES.

11:30 AM CLOSING REMARKS i

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i PRESENTATION T0 NRC JUNE 18, 1993 i

DENVER ATWOOD, COMMITTEE CHAIRMAN SOUTHERN NUCLEAR OPERATING COMPANY-h l

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COMMITTEE OVERVIEW l

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FORMED:

1991 o

MEMBERSHIP: ALL 22 DOMESTIC BWROG UTILITIES o

OBJECTIVE:

GENERICALLY ADDRESS GL 89-10 BWR ISSUES INTERRELATIONSHIPS 1

o MUG o

NUMARC TECHNICAL ADVISORY GROUPS AD HOC ADVISORY COMMITTEES o

EPRI PERFORMANCE PREDICTION PROGRAM o

LIMITORQUE o

KALSI ENGINEERING, INC.

o BWROG INTEGRATED RISK-BASED REGULATION COMMITTEE (PRA-MOV) o NRC WGF23/061893

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COMMITTEE OVERVIEW (CONTINUED)

COMPLETED COMMITTEE WORK o

TRENDING GUIDELINES o

VOLTAGE DROP CALCULATIONS / THERMAL OVERLOAD SIZING CRITERIA o

SUMMARY

OF RATE OF LOADING ISSUES o

oP TESTING ACCEPTANCE CRITERIA o

LIMITORQUE LIMITER PLATE POSITION PAPER o

MOV GROUPING CRITERIA o

INFORMATION EXCHANGE WGF23/061893

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.o C.QMMITTEE WORK IN PROGRESS i

o GL'89-10/IST PROGRAM COMPARISONS o

STEM / STEM NUT EVALUATIONS o

PERIODIC VERIFICATION (ROLE OF STATIC TESTING)'

o OPEN THRUST REQUIREMENTS o

APPENDIX J/GL 89-10 REQUIREMENTS SEPARATION o

MOV AGING EVALUATION o

NON-TESTABLE MOV JUSTIFICATIONS o

VOLTAGE DROP CALCULATION (AT START RATING)

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CONCLUSIONS ESTABLISHMENT OF MOV PROGRAM WARRANTED o

BETTER UNDERSTANDING OF DESIGN BASIS o

IMPROVED CONTROL OF SWITCH SETTINGS o

IMPROVED DIAGNOSTICS AND TRENDING o

IMPROVED IN-HOUSE EXPERTISE o

IMPROVED MOV MAINTENANCE AND RELIABILITY o

CORRECTED NUMEROUS MOV PROBLEMS BUT....

NRC - INDUSTRY NEEDS TO FOCUS ON GL 89-10 CLOSURE WGF23/061893

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MOV Program Building Blocks Temperature Valve Effects Factor Trends 1 Testing--

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l Distinction Must be Made Between the Program and Emerging issues

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Issues May Erode Integrity of Program if Not Recognized

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. DESIGN BASIS REVIEWS.

CONFIRM DESIGN BASIS CONDITIONS CONFIRM SAFETY FUNCTION e

o SIZING CALCULATIONS CONSIDER DEGRADED' VOLTAGE CONFIRM ACTUATOR SIZING CONFIRM STRUCTURAL ADEQUACY PERFORM. WINDOW CALCULATIONS-1 1-USE REASONABLE' DESIGN VALUES FOR' UNCERTAINTIES (E.s. VALVE FACTOR, STEM FRICTION FACTOR, ROL).

o BASELINE STATIC TEST TEST AND SET-UP PROCEDURES IN PLACE-CONTROL 0F SWITCH SETTINGS ESTABLISHED.

DIAGNOSTIC EQUIPMENT ACCURACY CORRECTLY! APPLIED -

o FLOW TEST (REASONABLE ALTERNATIVES TO "ALL VALVES-PRACTICABLE")

4 DEFINE VALVE GROUPS AND TEST-REPRESENTATIVE SAMPLE; EXTEND RESULTS TO UNTESTED MOVs BY EPRI METHOD OR-0THER REASONABLE APPROACH USE?EPRI EMPIRICAL EQUATION r.

oP TEST WAIVED FOR MOVs WITH LARGE: MARGIN

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UTILITY ACTIONS NEEDED TO ACHIEVE GL 89-10 OBJECTIVES ii (CONTINUED) i o

DESIGN CHANGES COMPARE FLOW TEST RESULTS TO SPECIFICATION j

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JUSTIFY OPERABILITY OR PERFORM DESIGN Cf8ANGES'IF SPECIFICALLY NOT CONSERVATIVE o

PERFORMANCE VERIFICATION USE PRA PRIORITIZATION METHODOLOGY FOR MOV RANKING ~-

-l DETERMINE RETEST' FREQUENCY CONSIDERING SUCH' THINGS l

AS IMPORTANCE, MAINTENANCE EXPERIENCE, FEMA,.RCM 3

WAIVE RETEST FOR "NON-SAFETY SIGNIFICANT" MOVs-

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CDF Sensitivity to MOV Failure Rate-CDF Sensitivity to MOV Failure Rate

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CLOSURE ON-ALL ISSUES SHOULD NOT BE REQUIRED-TO ACHIEVE GL 89-10 OBJECTIVE t

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REASONABLE ASSURANCE OF MOV OPERABILITY IS TYPICALLY I

DEFINED AS DESIGN' BASIS-MOV FAILURE RATE'BE11 DEEN 3/1000-j AND 10/1000.

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IMPLEMENTATION OF CORE PROGRAM DRIVES CDF WELL INTO j

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GL 89-10 WAS A CATALYST IN THE IDENTIFICATION OF SIGNIFICANT MOV PROBLEMS o

POTENTIAL FOR RISK REDUCTION JUSTIFIED MAJOR RESOURCE COMMITMENTS o

MOV PROGRAM BOUNDARIES MUST BE DEFINED AND MAINTAINED TO SUSTAIN FOCUS AND PRECLUDE DIMINISHING RETURNS o

UTILITY PROGRAMS SHOULD ENSURE THAT THE VAST MAJORITY OF THE MOV PROBLEMS WILL BE ADDRESSED IN RESPONSE TO GL 89-10 o

EXPANSION OF CURRENT MOV PROGRAM BOUNDARIES TO INCLUDE OUTSTANDING TECHNICAL ISSUES DOES NOT RESULT IN SIGNIFICANT RISK REDUCTION AND MAY ADVERSELY AFFECT MORE SIGNIFICANT SAFETY ISSUES WGF23/061893

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CURRENT NRC STAFF ACTIVITIES ON MOTOR-0PERATED VALVES INSPECTIONS UNDER PART 1 0F. TEMPORARY INSTRUCTION i

2515/109 TO REVIEW GENERIC LETTER:89-10' PROGRAMS HAVE BEEN COMPLETED'WITH THELEXCEPTION OF MILLSTONE.

NORTHEAST UTILITIES IS PERFORMING ASELF-ASSESSMENT OF MILLSTONE AND THE STAFF WILL EVALUATE THE NEED FOR A PART 1 INSPECTION BEFORE CONDUCTING A PART 2' INSPECTION OF GL 89-10 PROGRAM IMPLEMENTATION AT MILLSTONE.

j STAFF HAS~ INITIATED INSPECTIONS OF GL 89-10 PROGRAM l

IMPLEMENTATION:UNDER PART 2 0F TI 2515/109.

REVISION-I TO TI 2515/109 WAS ISSUED ON JUNE.14, 1993.

SUPPLEMENT 5 TO GL 89-10 ON MOV DIAGNOSTIC EQUIPMENT SHOULD BE ISSUED IN LA(E JUNE.

-SUPPLEMENT 6 TO GL 89-10 ON SCHEDULE AND GROUPING, AND OTHER PUBLIC QUESTIONS ON GL 89-10 SHOULD BE-ISSUED IN EARLY JULY.

BROOKHAVEN NATIONAL LABORATORY IS PERFORMING A STUDY OF CORE MELT-FREQUENCY RESULTING FROM VALVE' MISPOSITIONING IN~PWR PLANTS WITH COMPLETION SCHEDULED FOR EARLY AUGUST.

NRC STAFF MET-WITH EPRI ON. APRIL 22 TO DISCUSS.THE MOV PERFORMANCE PREDICTION PROGRAM.

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