ML20058M990
| ML20058M990 | |
| Person / Time | |
|---|---|
| Issue date: | 12/08/1993 |
| From: | Hiltz G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-683A NUDOCS 9312210180 | |
| Download: ML20058M990 (34) | |
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wasninoTon. o.c. 20ss5 0004 December 8, 1993 Project No. 683 ORGANIZATION:
Babcock and Wilcox Owners Group (BWOG)
PROJECT:
BWOG Generic License Renewal Program
SUBJECT:
SUMMARY
OF MEETING BETWEEN U.S. NUCLEAR REGULATORY COMMISSION STAFF AND BWOG REPRESENTATIVES TO DISCUSS THE BWOG GENERIC LICENSE RENEWAL PROGRAM (N0VEMBER 17,1993)
On November 17, 1993, representatives from the U. S. Nuclear Regulatory Commission (NRC) and representatives from the Babcock and Wilcox Owners Group (BWOG) Generic License Renewal Program (GLRP) met in Rockville, Maryland, to-discuss the status of the BWOG Generic License Renewal Program and the recent BWOG submittal of November 5, 1993, regarding an integrated plant assessment process demonstration. is the list of meeting attendees. contains copies of discussion material provided at the meeting by BWOG representatives.
Mr. Greg Robison, the Duke Power Corporation GLRP Project Engineer, provided a brief overview of the BWOG IPA process demonstration results. The decay heat removal / low pressure injection system, the diverse scram system, the emergency feedwater system, and the emergency diesel generator system were the systems selected by the BWOG to demonstrate its IPA process.
According to BWOG representatives, the individual plant results of the structure and component screening were consistent and comprehensive with respect to each plant's system boundaries and each plant's current licensing basis.
Most components were dispositioned in the IPA process through a condition monitoring evaluation and determined not to be subject to age-related degradation unique to license renewal.
BWOG representatives also concluded that there is no need to determine if a component function is active or passive and that the' IPA process should place strong reliance on existing programs to manage the effects of aging without detailed mechanistic evaluation.
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170128 GetuT4 CONTACT:
Tom Hiltz, NRR, PDLR 504-1105 3
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December 8, 1993 i
< BWOG representatives indicated that the BWOG will continue to participate in the Nuclear Management and Resources Council (NUMARC) effort to propose revision to the license renewal rule.
The BWOG plans to consolidate its system and component screening methodologies and complete several technical reports by early 1994. Several of these technical reports may be submitted to the NRC in 1994 and the BWOG is determining for which reports it will request that the NRC staff prepare a safety evaluation.
/s/
Thomas G. Hiltz, Senior Project Manager License Renewal And Environmental Review Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosures:
1.
List of Meeting Attendees 2.
Copies of Discussion Material Provided by BWOG Representatives cc:
See next page DISTRIBUTION:
Docket file PDR PDLR R/F TMurley/F.Mi ragl i a, 12G18 JCallan, 12G18 DCrutchfield, 11H21 WTravers, 11H21 OGC EJordan, MNBB3107 ACRS (10)
JMitchell, ED0 LPDR OCONEE LPDR 50-302 LPDR 50-313 LPDR 5%346 LPDR 50-289/320 DISTRIBUTION: via E-Mail PDLR Staff JVora, NLS217B SDroggitis, 3D23 CPetrone, 10A19 PDLR:LA PDLR; EPM,
PDLR:SC (f)L PDL&
CNorsworthy #
THilIz SReynolds W
SNerry 12/f/93 12/1/93 12/7/93 12/h/93 DOCUMENT NAME:
HILTZ 11/17 MEETING
SUMMARY
Project No. 683 Babcock Wilcox Owners Group Generic License Renewal Program cc:
Mr. Tony L. McConnell Regional Administrator, Region 11 Program Director U.S. Nuclear Regulatory Commission Generic License Penewal Program 101 Marietta St., N.W. Suite 2900 B&W Nuclear Service Company Atlanta, Georgia 30323 P.O. Box 10935 Lynchburg, Virginia 24506-0935 Mary E. O'Reilly Centerior Energy Corporation Mr. Robert B. Borsum 300 Madison Avenue B&W Nuclear Technologies Toledo, Ohio 43652 1700 Rockville Pike Suite 525 Mr. R. L. Gill Rockville, Maryland 20852 GLRP Licensing Coordinator c/o Duke Power Company Michael Laggart EC-09M Manager, Corporate Licensing P.O. Box 1006 GPU Nuclear Corporation Charlotte, North Carolina 28201-One Upper Pond Road 1006 Parsippany, New Jersey 07054 Regional Administrator, Region IV Chairman U.S. Nuclear Regulatory Commission Board of County Commissioners 611 Ryan Plaza Drive, Suite 1000 of Dauphin County Arlington, Texas 76011 Daughin County Courthouse Harrisburg, Pennsylvania 17120 Mr. James J. Fisicaro Director, Licensing Mr. Percy M. Beard, Sr.
Entergy Operations, Inc.
Vice President Route 3, Box 137G Nuclear Operations Russelville, Arkansas 72801 ATTN: Manager, Nuclear Operations Licensing Gerald Charnoff, Esq.
P.O. Box 219-NA-21 Shaw, Pittman, Potts Crystal River, Florida 34423-0219 and Trowbridge 2300 N. 5treet, N.W.
Mr. John R. McGaha Washington, DC 20037 Vice President, Operations Support Entergy Operations, Inc.
Earnest L. Blake, Jr., Esq.
P.O. Box 31995 Shaw, Pittman, Potts Jacksonville, Mississippi 39286 and Trowbridge 2300 N. Street, NW Mr. Robert W. Schrauder Washington, D.C.
20037 Manager, Nuclear Licensing Toledo Edison Company Regional Administrator, Region I 300 Madison Avenue U.S. Nuclear Regulatory Commission Toledo, Ohio 43652 475 Allendale Road King of
- Prussia, Pennsylvania Regional Administrator, Region III 19406 U.S. Nuclear Regulatory Commission 799 Roosevelt Road R. C. Widell, Director Glen Ellyn, Illinois 60137 Nuclear Operations Site Support Florida Power Corporation P.O. Box 219-NA-21 Crystal River, FL 34423-0219
Project No. 683 B&W Owners (continued)
'Mr. Donald C. Shelton Vice President, Nuclear -
Davis-Besse Centerior Service Company c/o Toledo Edison Company 300 Madison Avenue Toledo, Ohio 43652 William Dornsife, Acting Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P.O. Box 2063 Harrisburg, Pennsylvania 17120 Chairman Board of Supervisors of Londonderry Township R.D. #1 Geyers Church Road Middletown, Pennsylvania 17057 Mr. M.E. Patrick Compliance Duke Power Company Oconee Nuclear Site P.O. Box 1439 Seneca, South Carolina 29679 P
ENCLOSURE 1 Project No. 683 NRC/BWOG Meeting Generic License Renewal Program U.S. Nuclear Regulatory Commission Rockville, Maryland November 17, 1993 List of sattendees Name Title and Affiliation Robert Borsum BWNS Dave Firth BWNT Dan Fouts Project Engineer, Entergy Operatior.s Don Fultonberg Manager THI-l LRP, GPUN Robert Gill BWOG GLRP License Coordinator Nigel Goulding BWNT Tricia Heroux Electric Power Research Institute Thomas Hiltz Senior Project Manager, NRR/PDLR Steve Hoffman Senior Project Manager, NRR/PDLR Debbie Jackson Mechanical Engineer, NRR/PDLR Terri Kuhn Project Engineer, BWOG/GPUN Sam Lee NRR/PDLR Robert I. Lutz BWNT Tony L. McConnell Program Director, BWOG GLRP Jocelyn Mitchell NRC/0ED0 Rebecca Nease Senior Project Manager, NRR/PDLR Scott Newberry Director, NRR/PDLR Ron Parkhill Senior Mechanical Engineer, NRR/PDLR Charles Petrone Operations Engineer, NRR/RPEB Antony Pfeffer SERCH Licensing, Bechtel Harold Polk NRR/PDLR Mark Rinckel BWNT Gregory D. Robison Senior Engineer, BWOG/ Duke Power Vincent R. Roppel Project Engineer, BWOG/ Florida Power Corp.
Paul Shemanski Sr. Electrical Engineer, NRR/PDLR Deborah K. Staudinger BWOG Tom Tai Bechtel Frank Turski Project Engineer, BWOG/ Toledo Edison Ken Wilson Manager Nuclear Licensing, FPC Scott Wingate Nuclear Engineer, NUS Licensing
' ENCLOSURE 2 B&WOG GLRP IPA Process Demonstration.
November 17,1993 B&W OWNERS GROUP GENERIC LICENSE RENEWAL PROGRAM INTEGRATED PLANT ASSESSMENT PROCESS DEMONSTRATION Meeting with the NRC STAFF November 17,1993 1
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B&WOG GLRP IPA Process Demonstration Novemhei 17,1993~
B&W Owners Group (B&WOG) Utilities
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Duke Power Company Entergy Operations Inc.
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Florida. Power Corporation
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GPU Nuclear Corporation
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Toledo: Edison Company
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B&WOG GLRP IPA Process Demonstration November 17, 1993 IPA Process Demonstration Objectives Further definition and refinement of the technical process,
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prior to expending the resources required for a full-scale IPA Identification of problems and difficulties with implementation
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to provide early improvements to the IPA process To provide insight to the NRC
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Demonstrate generic applicability
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a Define ITLR Systems and their ITLR Functions I'
V STRUCTURE /COh!PONENT SCREENING Define population ofITLR Structures and Components and their ITLR Component Functions y
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ARDM PATH hiONITORING NO PATH Aging ARDUTLR l
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Evaluations Evaluations and Aging
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B&WOG GLRP IPA Process Demonstration November 17, 1993 IPA Process Demonstration System Selection Criteria Systems meet one or more of the ITLR requirements
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Generic applicability and ease of comparing results
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Encompass a wide variety of equipment types to properly
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exercise the process 6
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1 B&WOG GLRP IPA Precess Demonstration November 17, 1993 IPA Process Demonstration Selected Systems Decay Heat Removal (DHR)/ Low Pressure Injection-(LPI)
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System Diverse Scram System (DSS)
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Emergency Diesel Generator (EDG)
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B&WOG GLRP IPA Process Demonstration November 17, 1993 IPA Process Demonstration System /Uti:ity Responsibi:ity Summary SYSTEM
. ANO-1 CR-3 DB-1 ONS-1 TMI-1 DHR/LPI X
X X
DSS X
X X
EFW X
X X
EDG X
X X
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B&WOG GLRP IPA Process Demonstration Novemh2r 17,1993 Screening Summary System / Structure Screening Systems chosen met one or more of the ITLR requirements
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Systems chosen provided a representative scope of plant
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equipment For utilities addressing the same system, the ITLR system
=
functions were very similar 10 2
B&WOG GLRP IPA Process Demonstration November 17, 1993 Screening Summary Structure / Component Screening Results were consistent and comprehensive with respect to
=
system boundaries System boundaries remained plant specific and accounted for
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variations in the full scope of ITLR components screened The scope of electrical, I&C, and structural equipment
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included varied from plant to plant l
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B&WOG GLRP IPA Process Demonstration November 17, 1993 Screening Lessons Learned
. System / Structure and Structure / Component Screening
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should be performed in one step Consistent results were achieved independent of system
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boundaries and utility implementation procedures 12
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November 17, 1993 B&WOG GLRP IPA Process Demonstration Decay Heat Removal System (single Train shown)
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t B&WOG GLRP IPA Process Demonstration November 17, 1993' Component Evaluation Summary 4
Components selected to represent a diverse cross section of
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plant equipment Component ITLR functions may take one of two paths after
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determining the component is not routinely replaced Condition Monitoring Path ARDM Path A single component may have multiple ITLR functions
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l-evaluated along different paths 14
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4 November 17, 1993 B&WOG GL.RP IPA Process Demonstration Condition Monitoring Path Example Plant:
ANO-1 System: Decay Heat Removal (DHR)
Component Tag Number:
PDT-1402 Component Name:
Flow Transmitter ITLR Function (s):
Sense / Transmit Signal Question Yes No Comments Does a condition PDT-1402 is calibrated every monitoring, inspection, or X
refueling outage per ops 1304.001 test program exist?
and 1304.186. The ops include 1
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string / loop continuity checks and Does the program address X
contain acceptance criteria and the ITLR functions?
corrective actions if criteria are not Does the program monitor met.
ITLR functions by failure X
trend or reduced capability?
Does the program contain acceptance criteria to X
trigger corrective action?
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November 17, 1993 B&WOG GLRP IPA Process Demonstration ARDM Path Example Plant:
ANO-1 System: Decay Heat Removal (DHR)
Component Tag Number:
T-3 Component Name: BWST Tank ITLR Function (s):
Pressure Boundary Question Yes No Comments Are there aging X
Investigate general corrosion, mechanisms that could pitting, and stress relaxation defeat ITLR functions?
mechanisms If so, are they managed by-Program review is pending an existing program?
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D&WOG GLRP IPA Process Demonstration November 17, 1993 Component Evaluation Lessons Learned Most. components dispositioned through the condition
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momtoring path as having:no ARDUTLR l
Existing programs cover most ITLR components
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These existing programs are effectively managing the
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effects of aging t
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B&WOG GLRP IPA Process Demonstration Novemtzr 17. 1993 DHR/LPI Summary Disposition Category Number of Components ANO-1 CR-3 ONS-1 Routine Replacement 0
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Condition Monitoring Path 24 20 18 ARDM Path 4
5 13 Component. Evaluation incomplete 5
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n B&WOG GLRP IPA Process Demonstration November 17, 1993 DSS Summary Disposition Category Number of Components CR-3 DB-1 ONS-1 Routine Replacement 0
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ARDM Path 0
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Component Evaluation incomplete 0
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B&WOG GLRP IPA Process Demonstration November 17. 1993 EFW Summary Disposition Category Number of Components ANO-1 CR-3 TMI-1 Routine Replacement 0
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Condition Monitoring Path 16 16 11 ARDM Path 5
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Component Evaluation incomplete 1
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B&WOG GLRP IPA Process Demonstation November 17. 1993.
EDG Summary Disposition Category Number of Components ANO-1 DB-1 TMI-1 Routine ' Replacement 5
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Condition Monitoring Path 28 23 28 ARDM Path 0
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Component Evaluation incomplete 0
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B&WOG GLRP IPA Process Demonstration November 17, 1993 Process Summary System / Structure Screening
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ITLR system functions are the same with minor differences attributed to system designations, system boundaries, and variations in licensing bases.
Structure / Component Screening
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The results were consistent and comprehensive with respect to each plant's system boundaries and CLB Component Evaluation
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Most components dispositioned through the Condition Monitoring Path as having no ARDUTLR i
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B&WOG GLRP IPA Prcress Demonstration November 17,1993 Lessons Learned The. process used was overly complex and variable
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No need to identify all ITLR functions if component is routinely replaced No need to determine if a function is active or passive Credit should be taken for programs at the highest level
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Ensure credit is taken at commodity and/or system level, where possible e
23
B&WOG GLRP IPA Process Demonstration November 17. 1993 Lessons Learned Continued There are still evaluations within the.CLB that will require
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updating before extending operation Refurbishment needs to be better defined as related to
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managing specific aging effects 24 I
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' B&WOG GLRP IPA Preress Demonstration November 17. 1993 -
Conclusion The IPA Process should incorporate significant reliance on existing programs to manage the effects of aging without detailed mechanistic evaluation I
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B&WOG GLRP IPA Process Demonstration November 17, 1993
~GLRP Status 1993 Plan Participate in NUMARC effort to shape a revised LRR
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Consolidate System and Component Screening Methodologies
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Complete Technical Reports (no SER request) a RC Pump Borated Water. Storage Tank Decay Heat Drop Line Continue development of 1994 Technical Reports
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Site Specific License Renewal Work a
B&WOG GLRP IPA Process Detnorstration November 17, 1993
'GLRP Status 1994 Plan Continue participation in NUMARC effort to shape a revised
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LRR Respond to industry efforts to validate / test IPA Process
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Options Develop a LRA Content / Format Guideline Document (NRC
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review /no-SER)
Obtain SER on System Screening Methodology
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Complete ARDM Report (no SER)
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L B&WOG GLRP IPA Process Demonstration November 17, 1993 GLRP Status 1994 Plan Complete enveloping technical reports on long-lived passive
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components (Selected reports to NRC for review /possible SER request).
PRZ and PRZ Heaters CRDM. Nozzle Reactor Vessel Reactor Internals Tank Commodity Piping and Valve Body Commodity NSSS Supports Steam Generator a.
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. B&WOG GLRP IPA Process Demonstration November 17, 1993
'GLRP Status 1994 Plan Site Specific License Renewal Work
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Component Screening MR implementation coordination with LR Program Assessment Utility Administrative Controls l
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