ML20149J551
| ML20149J551 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/29/1994 |
| From: | Gwynn T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Yelverton J ENTERGY OPERATIONS, INC. |
| References | |
| GL-89-10, NUDOCS 9501060031 | |
| Download: ML20149J551 (50) | |
Text
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> teco, UNITED STATES i-
,g NUCLEAR REGULATORY COMMISSION y..
j j
REGION IV o,
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611 RYAN PLAZA DRIVE, SUITE 400 e
AR LINGTON, TEXAS 76011 8064 UEC 2 9 ;994 Entergy Operations, Inc.
ATTN:
J. W. Yelverton, Vice President Operations, Arkansas Nuclear One 1448 S.R. 333 Russellville, Arkansas 72801-0967
SUBJECT:
~ MEETING TO REVIEW GENERIC LETTER 89-10 STATUS This refers to the meeting conducted at the Arkansas Nuclear One site on October 27, 1994.
This meeting related to discussions of the status of actions to complete your commitments to NRC Generic Letter 89-10, " Safety-Related Motor-0perated Valve Testing and Surveillance." We consider your efforts to enhance the design margin capability of your motor operated valves i
to be a strength. We understand, based on these discussions, that you plan to submit completion letters by August 6, 1995, and March 3, 1996, for Units 1 and 2, respectively.
The meeting was attended by those listed in Enclosure 1.
The meeting agenda and copies of the presentation handouts are provided in Enclosure 2.
The meeting was considered beneficial and provided an open forum for discussion-between the NRC staff and the Arkansas Nuclear One staff in attendance.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter will be placed in the NRC's Public Document Room.
Should you have any questions concerning this matter, we will be pleased to discuss them with you.
Sincerely, 7
L
/
/T Thomas P. Gw nn, ire tor Division of ea or S 1fe y Dockets:
50-313 50-368 Licenses:
DPR-51 NPF-6 i
Enclosures-i 1.
Attendance List 2.
Licensee Presentation cc w/ Enclosure 1:
(see next page) 9501060031 941229 PDR ADOCK 05000313 P
PDR i
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Entergy Operations, Inc. cc w/ Enclosure 1:
Entergy Operations, Inc.
ATTN: Harry W. Keiser, Executive Vice President & Chief Operating Officer P.O. Box 31995 Jackson, Mississippi 39286-1995 Entergy Operations, Inc.
ATTN: Jerrold G. Dewease, Vice President Operations Support P.O. Box 31995 Jackson, Mississippi 39286 Wise, Carter, Child & Caraway ATTN:
Robert B. McGehee, Esq.
P.O. Box 651 Jackson, Mississippi 39205 Honorable C. Doug Luningham County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Winston & Strawn ATIN:
Nicholas S. Reynolds, Esq.
1400 L Street, N.W.
Washington, D.C.
20005-3502 Arkansas Department of Health ATTN:
Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management 4815 West Markham Street Little Rock, Arkansas 72201-3867 B&W Nuclear Technologies ATIN:
Robert B. Borsum Licensing Representative 1700 Rockville Pike, Suite 525 Rockville, Maryland 20852 Admiral Kinnaird R. McKee, USN (Ret) 214 South Morris Street Oxford, Maryland 21654
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Entergy Operations, Inc. ABB Combustion Engineering Nuclear Power ATTN: Charles B. Brinkman Manager, Washington Nuclear Operations 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 i
,h Entergy Operations, Inc. 1 bcc:
E-Mail to Tom Scarbrough bcc distrib. by RIV:
L. J. Callan Resident Inspector Branch Chief (DRP/D)
Leah Tremper (0C/LFDCB, MS: TWFN 9E10) t MIS System DRSS-FIPB RIV File Branch Chief (DRP\\TSS)
Project Engineer (DRP/D)
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n ENCLOSURE 1 ATTENDANCE LIST 1.1 Licensee Participants v
C. Little, Unit Coordinator, Design Engineering S. Bennett, Acting, Supervisor Licensing T. Ott, Engineering' Instrumentation and Control, Design Engineering E. Miller, Senior Assistant Engineer, Design Engineering R. Lane, Director, Design Engineering M. Smith, Supervisor, Licensing
.T. Mitchell, Unit 2 System Engineer Manager C. Turk, Manager, MCS, Design Engineering G. Werner, III, Supervisor, MCS, Design Engineering M. Lloyd, Senior Lead Engineer, PSA/NED, Design Engineering S. Pohl, Senior Lead Engineer, Motor-0perated Valves, Unit 2 System Engineering B. Hollowoa, Senior Engineer, Motor-0perated Valves, Unit 2 System Engineering D. Mims, Director, Licensing W. Rowlett, Senior Lead Engineer, Mechanical System T. Grant Ehren, Senior Engineering, MCS G. Hines, Engineer III, Design Engineering R. Gordon, Supervisor, System Engineering (Diagnostic)
W. Roberts, Supervisor, Design, Motor-0perated Valves J. Haley, Licensing Specialist, Licensing 1.2 NRC Participants T. Westerman, Chief, Engineering Branch C. Myers, Reactor Inspector, Engineering Branch 1.3 NRC Participants by Telephone T. Scarbrough, NRR G. Pick, Project Engineer, Project Branch D M. Runyan, Reactor Inspector, Engineering Branch
ENCLOSURE 2 ARKANSAS NUCLEAR ONE e
i TO REVIEW GL 89-10 STATUS
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OCTOBER 27,1994
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l AGENDA 1.
INTRODUCTION AND OVERVIEW ll.
IR 92-18 AND 93-13 FOLLOW-UP ll1.
ITEMS COMPLETE BY JUNE 28 FOR GL 89-10 IV.
GL 89-10 CLOSURE V.
MARGIN ENHANCEMENT AND BOUNDING OF UNCERTAINTY VI.
PROGRAM SCHEDULE Vll.
IFl 9411-01 FOLLOW-UP
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SECTION I il INTRODUCTION AND PROGRAM OVERVIEW t
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a ANO MOV PROGRAM GL 89-10 SCOPE &
STATUS Unit 2 Scope Unit 1 Scope
- Valves: 115
- Valves: 132
- DP Cand: 70
- DP Cand: 93 Unit 2 Status Unit 1 Status
- Static Tests: 115
- Static Tests: 132
- DP Tests: 65
- DP Tests: 68
- Stage 2 Comp: 44
- Stage 2 Comp: 34 Over 100 MOVs have been modified to improve margins and meet requirements i
All Torque Switch Settings Evaluated Operable Considering "Best Available Data" Including Six Under Present Design Criteria Minimum Thrust
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MOV PROGRAM STRENGTHS LARGE PERCENTAGE OF MOVS TESTED DYNAMICALLY PROACTIVE HISTORY OF MODIFICATIONS STRONG TEAMWORK BETWEEN TESTING AND DESIGN GROUPS EMERGENT ISSUE RESPONSE
MOV PROGRAM STRENGTHS (CONT.)
USE OF PRA TO FOCUS RESOURCES i
PROACTIVE APPROACH TO
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GATE VALVE PRESSURE LOCKING / THERMAL BINDING 1
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DATA AND FAILURE TRENDING
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il MOV PROGRAM CHALLENGES ORIGINAL ACTUATOR SIZINGS BASED ON MINIMAL CONSERVATISM APPROXIMATELY 100 MOVs TO 4
BE REVIEWED FOR MARGIN ENHANCEMENT
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STAGE 2 COMPLETION ACTIVITIES RECONCILIATION OF SEISMIC CALCULATIONS AND SAR STATEMENTS
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- 64 OF ORIGINAL 69 NOW SET ABOVE DESIGN CRITERIA IN SAFE DIRECTION 3 OUTLIERS TO BE MODIFIED AT NEXT i
OUTAGES 1 OUTLIER TO BE RESET AT NEXT OUTAGE l
1 OUTLIER JUSTIFIED AT PRESENT l
SETTING l
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l ALL OUTLIERS ADDRESSED BY l
CONDITION REPORTS WITH
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OPERABILITY REVIEWS i
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IR 93-13, INSPECTOR' FOLLOW-UP i
ITEM NO.1
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i AC VOLTAGE LESS THAN 4
70 %
- THREE VALVES IDENTIFIED
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- ALL OPERATE AT LEAST THREE MINUTES AFTER ES ACTUATION
- VOLTAGES RECALCULATED TO GREATER THAN 70%
)
==
IR 93-13, INSPECTOR FOLLOW-UP ITEM NO. 4 TORQUE SWITCH REPEATABILITY AT SETTING OF 1.0 t
l
- ALL SETTINGS OF 1.0 ANALYZED IN ER 93-R-0004-02 l
- ALL MOVS OPERABLE
- SPECIAL HANDLING OF 1.0 SETTINGS f
- Setpoint Calculation Reanalysis
- Multiple Strokes to Determine Actual 4
Repeatability
IR 93-13, INSPECTOR FOLLOW-UP ITEM NO. 5 2CV-5057-2 CORRECTIVE ACTIONS:
USE OF C10 0R C11 ALL ACTIONS OF CR 2-93-0144 COMPLETED 2CV-5057-2 RETESTED AND FULLY OPERABLE ANO EXTRAPOLATIONS NOW USE GREATER OF C10 0R C11 FOR BOTH IMMEDIATE OPERABILITY DETERMINATIONS AND POST-TEST ANALYSES
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IR 93-13, INSPECTOR FOLLOW-UP ITEM NO. 8 DP TEST TRACE MARKINGS CV-3812 DISPOSITION 6
- DP TRACE MARKINGS PREVIOUSLY ADDRESSED
- MEDP CALCULATION FOR CV-3812 REVISED FOR CLOSE POSITION f
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IR 93-13, INSPECTOR FOLLOW-UP ITEM NO. 9 LOAD SENSITIVE BEHAVIOR EXTRAPOLATION
- ANO NOW EXTRAPOLATES LSB TO 70% MEDP
- ALL DYNAMIC TESTS ANALYZED WITH STRAIGHT LINE EXTRAPOLATION METHODS 1
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IR 93-13, INSPECTOR FOLLOW-UP ITEM NO.12 PRESSURE LOCKING /
THERMAL BINDING OF GATE VALVES l
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THERMAL BINDING HISTORY l
RESULTS OF PHASE 1 - REVIEW OF PAST ANO ACTIONS
- PREVIOUS EVALUATIONS FOR SOER 84
-07 CONSIDERED INCOMPLETE f
- PREVIOUS REVIEWS DID NOT CONSIDER ALL SYSTEM DESIGN PARAMETERS AND MODES OF OPERATION
- PREVIOUS EVALUATIONS WERE NOT LIVING DOCUMENTS
- DOCUMENTATION FROM PREVIOUS REVIEWS / EVALUATIONS WAS INCOMPLETE OR MISSING
=
THERMAL BINDING HISTORY PHASE 2 INITIATED EARLY 1994 TO EVALUATE GL 89-10 VALVES
- SCREEN FOR REQUIRED SAFETY FUNCTION TO OPEN
- EVALUATE SYSTEM FUNCTION AND DESIGN PARAMETERS AGAINST l
COMPONENT CAPABILITIES USING AN ENTERGY ANALYSIS METHOD l
- EVALUATE CAPABILITY OF MOV TO OPEN AGAINST CALCULATED FORCES
- CONSIDER PREVIOUS VALVE FUNCTION UNDER SIMILAR THERMAL CONDITIONS t
==
=
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THERMAL BINDING CURRENT ANALYSES INITIAL POPULATION OF 181 GATES h
- 78 in Unit 1
- 103 in Unit 2 106 - ELIMINATED WITH NO SAFETY I
FUNCTION TO OPEN
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EVALUATING 75 FOR PL/TB FOUND INDICATIONS THAT 45 POTENTIALLY SUSCEPTIBLE PRELIMINARY RESULTS OF THE f
ANALYSIS DEMONSTRATE THAT ALL VALVES ARE OPERABLE PLANNED TO COMPLETE BY END OF 1994
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THERMAL BINDING FUTURE ACTIONS l
PROCEDURAL AND EQUIPMENT MODIFICATION RECOMMENDATIONS l
- PRIORITIZATION BASED ON
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ANALYSIS RESULTS AND PRA RANKING
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- CONSIDERATION OF OTHER FACTORS SUCH AS INCREASED SEAT LEAKAGE FOLLOW INDUSTRY EVENTS, STUDIES, TESTS AND PEER GROUPS
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EVALUATE REMAINING POPULATION OF SAFETY RELATED ACTIVE VALVES, l.E. AOV AND SELECTED MANUAL GATES
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SECTION 111 l
ITEMS COMPLETED BY JUNE 28,1994 FOR GL 89-10 l
c DESIGN BASIS REVIEW s
MEDP CALCULATIONS COMPLETED TO INCLUDE DESIGN FLOWS AND h
TEMPERATURES SEISMIC CALCULATIONS COMPLETED TO COMBINE THRUST / TORQUE AND SEISMIC LOADS CONCURRENTLY
- VENDOR WEAK LINK CALCULATIONS UNDERVOLTAGE CALCULATIONS
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DESIGN INPUT PARAMETER VALIDATION
- DYNAMIC TEST RESULTS SHOW DESIGN CRITERIA ARE ADEQUATE
- INFORMATION FROM DYNAMIC TESTS IS USED IN EVALUATION OF NON-TESTABLE MOVS s
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- STATIC AND DYNAMIC TEST DATA REVIEWED AND INPUT INTO SETPOINT CALCULATION
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_k STATUS REPORTS The adequacy of the current torque switch settings for all ANO GL 89-10 MOVs have been reviewed and the results are summarized in ER 94-R-1006-011: Unit 1) and ER 94-R-2007-01 I Unit 2)
Results are:
Using Best Available Data as part of the review process, all MOVs are considered operable at their current torque switch settings Six MOVs have been identified as marginal as discussed previously These documents will be periodically revised to reflect new test data and other best available information
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ANO MOV PROGRAM DATABASE This database established to capture and track major open issues related to each valve / actuator in the MOV program Potential future uses:
- test data communication between Design and System Engrg
- actuator setup information (not setpoints as defined by calc)
- MEDP and system information
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I ANO MOV PROGRAM Performance Trending 1R9 2R8 1R10 &
1R11 2R10 40 3R6 35
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GL 89-10 CLOSURE l
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CLOSURE DATES
- EXTENSION APPROVED CLOSURE DATES: 120 DAYS AFTER FOURTH REFUELING OUTAGE l
-UNIT 1 - AUGUST 1,1995
- UNIT 2 - MARCH 1,1996
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ACTIVITIES (ALL NUMBERS ARE APPROXIMATE)
DISPOSITION OF SEISMIC ISSUES l
COMPLETE INITIAL DYNAMIC TESTS - 30 COMPLETE STAGE 2 ANALYSES 100 - DYNAMIC TEST STRAIGHT LINE
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EXTRAPOLATIONS USING ENTERGY AND EPRI FINDINGS 40
- USING ANO DATA, EPRI FLOW LOOP RESULTS, EPRI PPM OR OTHER 30 -
USING LARGE MARGIN JUSTIFICATION
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l SECTION V MARGIN ENHANCEMENT /
BOUNDING OF UNCERTAINTY
ANO APPROACH
- ENGINEERING STUDY OF EACH SMALL MARGIN MOV (96)
- IDENTIFY POSSIBLE ACTIONS FOR MARGIN IMPROVEMENT
- OPEN IN THE SAFE DIRECTION
- TORQUE SWITCH RESETS
- EVALUATE DESIGN BASES
- PERIODIC DYNAMIC TESTING
- MODIFICATIONS
- VERIFICATION OF CONTINUED CAPABILITY BY PERIODIC TESTING
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METHODOLOGY ALL GL 89-10 VALVES IN PRA MODEL RANKEDIH, M, L, LL;l ACCORDING TO R.A.W. IMPORTANCE CONSISTENT WITH EPRI RECOMMENDATIONS I
RANKINGS INCLUDE VALVES WHOSE FFMS ARE NOT IN THE PRA 4
EXPERT PANEL REVIEW AND REVISION OF PRA RANKINGS IREVISED UPWARD, IF APPROPRIATE;l EXPERT PANEL PROVIDES RANKING FOR MOVS NOT IN PRA RANKS USED AS INPUT TO I
DETERMINE TEST FREQUENCY AND TO PRIORITIZE MARGIN
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ENHANCEMENTS
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PROPOSED MARGIN TARGET ABOVE DESIGN CRITERIA INITIAL TARGET FOR GATE AND GLOBE VALVES
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35% FOR SAFETY SIGNIFICANCE HIGH INITIAL TARGET FOR BUTTERFLY VALVES
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20% FOR SAFETY SIGNIFICANCE HIGH
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Based on closed margins only SMALL MARGIN (96)
- HIGH & MEDIUM 36
- LOW & LOW-LOW 60 LARGE MARGIN (151)
- HIGH & MEDIUM 21
- LOW & LOW-LOW 130
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PERIODIC VERIFICATION RETEST ALL STATICALLY BASED ON GRADED APPROACH RETEST INDIVIDUAL VALVES DYNAMICALLY IF NECESSARY AS AN ALTERNATIVE TO MODS EVALUATE USE OF SELECTIVE DYNAMIC TESTING TO VERIFY MARGIN RETENTION
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PROGRAM CLEAN-UP ACTIVITIES EVALUATE EFFECTS OF
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EXTEND RETESTING FREQUENCIES USING GRADED APPROACH 4
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SECTION Vil INSPECTOR FOLLOWUP ITEM 9411-01 (CLOSURE OF NRC INSPECTION REPORT 89-200) l
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.~r.: '.TT~ :': " ~ r - ".' ~ T:' - '. :7.. : :::!~~ ^. ~ : ': 'T T.T ~ :': :"2.72: = = = = W 27T IFl 313/9411-01 SEISMIC QUALIFICATION OF MAIN FW ISOLATION VALVES ACTION
- Per IFl 9411-01 " Licensee agreed to review their licensing basis to determine the requirements for the motor-operated valves" ( Concurrent seismic /LOCA)
REVIEW APPROACH 1
- ANO reviewed the following documents for ANO licensing basis:
- Research covered the following areas:
Structural Integrity of Pressure Retaining Components Seismic Classification of Components Reactor Coolant Pressure Boundary Valves and Components Reg Guide 1.48
O 1
IFl 313/9411-01 SEISMIC QUALIFICATION OF MAIN FW ISOLATION VALVES FINDINGS ANO-1 SAR 1.4.2 (GDC 2) does not require specific concurrent seismic and LOCA qualification SAR 5.2.1.2 requires combined loads for Cat 1 Structures SAR 4.1.2.5.2 requires combined loads for RCS pressure retaining components SAR 3.1.3.4/3.2.4.1 requires vessel and internals to meet combined loads SAR 4.4.4.1 (Q&R 4.32) requires active valves in RCPB to meet combined loads ANO-2 (SAR 3.1.1) GDC 2 does not require specific seismic /LOCA qualification SAR 3.8.1.3.3 requires combined loads for Cat 1 Structures SAR 5.2.1.1 requires combined loads for RCS pressure retaining components i
SAR 4.2.4.4 requires vessel and internals to meet combined loads SAR 5.2.1.6/.17 requires active valves in RCPB to meet combined loads SAR 6.3.2.12.2 additionally requires concurrent loading of Safety injection System active valves SAR 3.9.2 requires seismic plus operational loads for Seismic Category I, Class 2 and 3 valves I
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IFl 313/9411-01 SEISMIC QUALIFICATION OF MAIN FW ISOLATION VALVES RESULTS
SUMMARY
ANO-1 No NRC Design Requirements Exist based on ANO Operating License issuance which requires Concurrent Seismic and LOCA loading
- ANO Commitments for Concurrent Seismic &
LOCA are:
Cat.1 Structures Reactor, Reactor internals, and Reactor Coolant System Active Valves which are part of Reactor Coolant Pressure Boundary ANO-2
- Same as ANO-1 plus Safety injection System Active Valves for Concurrent Seismic & LOCA Loads
- Other Category I ASME Class 2 and 3 active valves require seismic plus operational loads CONCLUSION ANO licensing basis for concurrent seismic and LOCA loading is applicable to all active reactor coolant pressure boundary valves for both units and ANO-2 SIS valves based on ANO commitments. Being documented in ANO Engineering Report 94-R-0004-01.
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IFl 313/9411-01 SEISMIC QUALIFICATION OF MAIN FW ISOLATION VALVES BACKGROUND
- Original Seismic Calculation did not qualify the valves for current combined loading or horizontal stem orientation
- NRC requested seismic calculation to be done by Anchor Darling (IFl 89-200-14)
- Calculations revised by ANO contractor rather than Anchor Darling
- NRC requested in IFl 9411-01 that ANO obtain concurrence from Anchor Darling on ANO calculations l
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IFl 313/9411-01 SEISMIC QUALIFICATION OF MAIN FW ISOLATION VALVES 1
CURRENT STATUS
- ANO requested Anchor Darling review of i
calculations and update original seismic qualification
- Anchor Darling stated ANO calculation conservative
- Anchor Darling declined to update original seismic qualification
- Anchor Darling stands behind their original seismic qualification
- To meet design goal, supplemental calculation produced based on Anchor Darling weak link calculation (1986) using equivalent pressures and combined seismic and thrust loads l
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