ML20045A408

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Summary of 930413 Meeting W/B&Wog in Rockville,Md Re Status of B&Wog Generic License Renewal Program.Attendance List & Presentation Matl Encl
ML20045A408
Person / Time
Issue date: 05/03/1993
From: Hiltz T
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
PROJECT-683A NUDOCS 9306100211
Download: ML20045A408 (33)
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Text

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'o UNITED STATES 8'

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NUCLEAR REGULATORY COMMISSION

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W ASHINGTON, D. C. 20555 3 e May 3, 1993 g

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 (NRC) STAFF AND BWOG REPRESENTATIVES TO DISCUSS THE BWOG GENERIC LICENSE RENEWAL PROGRAM On April 13, 1993, representatives from the U.S. NRC and representatives from the BWOG Generic License Renewal Program met in Rockville, Maryland, to discuss the status of the BWOG Generic License Renewal Program (GLRP). is the list of meeting attendees. contains a copy of the presentation material discussed at the meeting.

Mr. McConnell, the Program Director for the BWOG GLRP, presented an executive overview of the status of the GLRP. Mr. McConnell noted that the BWOG regarded the timely decision about a change to 10 CFR Part 54 (the license renewal rule) as potentially affecting the progress of the GLRP. The BWOG GLRP will not undergo significant growth until after considering the NRC's final decision regarding a rule change. He further emphasized that the final license renewal process must be legally defensible and noted that the BWOG had requested an independent legal analysis to examine license renewal options which may be exercised consistent with the current version of the license renewal rule.

Hr. McConnell discussed the BWOG GLRP's revised process flowchart for performing an integrated plant assessment (IPA).

BWOG representatives noted that the revised process flowchart contained some significant differences from the previous version.

BWOG representatives indicated that the use of probabilistic risk assessment (PRA) was clarified and the PRA will only be used indirectly by its use in implementing the maintenance rule.

Furthermore, the revised IPA process flowchart now requires that age-related degradation unique to license renewal be specifically determined and enhances the importance of the BWOG proposed technical report which will discuss age-related degradation mechanisms.

BWOG representatives illustrated the flowchart process using several system and component examples.

The staff agreed that the revised BWOG GLRP IPA process flowchart contained substantive changes from the previous version discussed at the March 16, 1993, BWOG GLRP meeting.

The staff did not discuss or decide whether the revised BWOG approach was acceptable.

The staff noted that the process for screening systems and components as not unique to license renewal differed from l

information previously discussed with BWOG representatives.

Previous

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hsd RET E TO R E M ID H E I,W M B

_ 0211 930610 930503 U

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A PDR

. discussions with the staff indicated that the BWOG expected the majority of systems, structures, and components to be dispositioned in the license renewal assessment process through an effective program evaluation.

The staff indicated that a comparison of the revised BWOG IPA process flowchart with the staff's flowchart discussed in SECY-93-049, " Implementation of 10 CFR Part 54,

' Requirements for Renewal of Operating Licenses for Nuclear Power Plants,'"

would greatly aid the staff's review of the revised BWOG process.

BWOG representatives stated that they will submit the GLRP component screening process to the NRC by May 5, 1993. The next meeting to discuss the status of the BWOG GLRP was tentatively scheduled for May 11, 1993.

Original signed by Thomas G. Hiltz, Senior Project Manager License Renewal and Environmental Review Project Directorate Associated Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

Enclosures:

1.

List of Attendees 2.

Copy of Presentation l

Material cc:

See next page DISTRIBUTION:

D.cL h Gentral File PDR PDLR R/F TMurley, FMiraglia,12G18 JPartlow, 12G18 WTravers, 11H21 SNewberry, llF23 FAkstulewicz, 11F23 THiltz, 11F23 LLuther, 11F23 OGC EJordan, MNBB3701 NRC Participants ACRS (10)

WRussell, 12G18 JHopkins, 13E21 JVora,NLS217By GGrant, 17G21 SDroggitis, 3D23 PDLR:LA PDLR:.

PDLR:SCL [ N LLuther THih FAkstud[icS i

6'A/ S /93 4/f/ /93 G/3/93Y OFFICIAL DOCUMENT COPY: HILTZ 4/13 BWOG MTG.

SUMMARY

i Project No. 683 Babcock Wilcox Owners Group Generic License Renewal Program cc:

Mr. Tony L. McConnell Regional Administrator, Region II Program Director U.S. Nuclear Regulatory Commission Generic License Renewal 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 ATIN: 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. Street, 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 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 i

Mr. M.E. Patrick Compliance Duke Power Company Oconee Nuclear Site P.O. Box 1439 Seneca, South Carolina 29679 e

Project No. 683 List of Attendees NRC/BWOG Meeting Generic License Renewal Program US Nuclear Regulatory Commission One White Flint North Room 1-F-7/1-F-9 Rockville, Maryland April 13, 1993 Name Title and Affiliation Tony McConnell BWOG GLRP, Program Director Frank Akstulewicz Section Chief, NRR/PDLR Raj Anand Project Manager, NRR/PDLR Robert Borsum BWNS Lynn Connor Southern Technical Services Eve Fotopoulos SERCH Licensing, Bechtel Daniel W. Fouts Project Engineer, BWOG/Entergy John Giddens WOG LCM /LR Working Group Vice Chairman Robert Gill BWOG GLRP License Coordinator William R. Gray BWNS Program Manager r

Gregory M. Gurican Sr. Corp Nuclear Licensing Eng., GPUN Tricia Heroux Electric Power Research Institute Thomas Hiltz Senior Project Manager, NRR/PDLR Deborah A. Jackson Mechanical Engineer, NRR/PDLR Terri M. Kuhn Project Engineer, BWOG/GPUN P.T. Kuo Section Chief, NRR/PDLR Mindy Landau Staff Assistant, NRC/0EDO John W. Lawrence Shaw, Pittman, Potts & Trowbridge Rebecca Nesse Senior Project Manager, NRR/PDLR Scott Newberry Director,NRR/PDLR Roger Newton WOG LCM /LR Working Group Chairman William T. O' Conner Project Engineer, BWOG/ Toledo Edison Ron Parkhill Senior Mechanical Engineer, NRR/PDLR Charles Petrone Operations Engineer, NRR/DRIL Steven A. Reynolds Technical Assistant, NRR/PDLR Mark A. Rinckel BWOG Gregory D. Robison Senior Engineer, BWOG/ Duke Power Vincent R. Roppel Project Engineer, BWOG/ Florida Power Corp.

Jeff Sharkey Senior Operations Engineer, NRR/PDLR Deborah K. Staudinger BWOG Tom Tai Bechtel David Tang NRR/PDLR William Travers Deputy Associate Director, NRR/ADAR Doug Waters NUMARC

ppigM B&WOG GLRP IPA PROCESS f

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l SCREENING Define ITLR Systems l

and Their ITLR Functions l

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l and their ITLR Functions

,_______________________________________________________________o________________________________________________________________-,

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I l COMPONENT ASSESSMENT &

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(Note 2) l Document Bases l

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EVALUATION Required. Create New Program,

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l ENCLOSURE 2~

NOTES FOR B&WOG GLRP IPA PROCESS 1.

An ITLR component function can be assured with a performance-based program if:

A.

The ITLR component function is active.

OR B.

Both of the following conditions are met for passive functions:

1.

If the component ITLR function is lost due to aging, it will not result in the loss of any ITLR system function, and 2.

If the component ITLR function is lost due to aging, it would be revealed by normal operation and/or surveillance.

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PfBLMiNARY NOTES FOR B&WOG GLRP IPA PROCESS (CONTINUED)

L A performance-based program effectively manages age-related degradation if:

2.

A.

Functional failure of the component is detectable (e.g.,

Technical Specifications).

i B.

Performance (e.g., failure trend, reduced capability) is monitored by a plant program (e.g., Maintenance Rule compliance program).

C.

Acceptance criteria exist to trigger corrective action programs.

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Commodity reports will contain the following:

Commodity definition (e.g., low-voltage cables inside containment).

i A.

B.

Evaluation of plausible ARDMs.

Description of alternatives to manage aging (e.g., analysis, inspection, C.

component redesign).

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PRE.MINARY NOTES FOR B&WOG GLRP IPA PROCESS (CONTINUED)

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. 3 NOTES FOR B&WOG GLRP IPA PROCESS pp; gj g y (CONTINUED) i 5.

Existing programs are effective to manage aging if:

history shows' that replacement criteria (periodic, or Operating A.

performance-or condition-based) are satisfactory to prevent loss of component ITLR function.

OR i

B.

Both of the following conditions are met:

l For plausible ARDMs, the programs detect age-related degradation of 1.

-l the component /part prior to loss of component ITLR function.

2.

Acceptance criteria exist that trigger corrective action programs.

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RCS System ITLR functions of interest:

Maintain primary pressure boundary.

Component ITLR Function: Maintain primary pressure boundary.

1. Can component function be assured with performance-based program?

1.A Function is Not Active 1.B.1 If component function lost, then system function lost.

Answer is NO

3. RCS pressure boundary integrity function not covered by commodity report
5. Existing programs effective?

Plausible ARDMs = Various Types of Corrosion 5.A.

No periodic replacement 5.B.1 ISI detects degradation due to corrosion 5.B.2 ISI has acceptance criteria and corrective action programs.

Answer is YES Action:

Document program bases.

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Transport decay heat to interfacing systems.

Component ITLR Function: Provide flow coastdown capability to prevent exceeding core DNBRiimits during accident scenarios.

1. Can component ITLR function be assured with performance-based program?

1.A Function is Active Answer is YES

2. Existing performance-based program effective?

2.A Failure detected by coastdown time surveillance test (Tech. Spec.)

2.B MR program monitors RCP performance via plant-level performance: capacity factor and reviews for repetitive failures 2.C Specific limits for capacity factor and repetitive failure are defined in MR performance criteria Procedure requires corrective action when an above limit reached Answer is YES Action:

Document program bases.

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,__________________--_______________________-o._________________y__No_______________________,,_,,___________,____

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Examole 3 - Manual Gate Valve: Pressure Boundary Function

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Maintain primary pressure boundary.

Component ITLR Function: Maintain primary pressure boundary.

1. Can component ITLR function be assured by performance-based program?

1.A Not Active.

1.B.1 Failure causes loss of RCS system function - Answer is NO Answer is NO 3.

Component covered by commodity report (Manual Gate Valves <4")

r Action:

Utility verify that commodity report applies and that effective age management programs in place.

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bli. );hh Example 4 - Containment Building Liner: Pressure Boundary Function Structure: Reactor Building Structure ITLR Functions of Interest: Prevent offsite release of radioactive material, i.e. Pressure Boundary Component ITLR Function: Provide high degree of leak-tightness to prevent off site release.

1. Can component function be assured with performance-based program?

1.A Function is not active.

1.B.1 Loss of component function could result in loss of system function.

Answer is NO 3.

Containment liner pressure boundary function not covered by commodity report.

5.

Existing programs effective?

Plausible ARDMs = Various types of corrosion.

5.A Not routinely replaced.

5.B.1 ISI can detect degradation.

5.B.2 ISI program has acceptance criteria and corrective action programs.

Answer is YES Action:

Document program bases.

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Examole 5 - Primary Pioe Hanaer: Support Function g-l:

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(CR RCH-629: Hanger for 2.5" SS line) i Considered to be part of reactor building structure.

Structure iTLR Function:

Provide physical support for for systems and components inside building.

Component ITLR Function: Support systems and components in reactor building.

1. Can component ITLR function be assured with performance-based program?

1.A Not active.

1.B.1 Failure of single hanger will not result in loss of system ITLR function.

1.B.2 Single hanger failure will not be revealed.

Answer is NO

3. Component covered by commodity report for hangers.

Action:

Utility verify that commodity report applies und that effective age-management programs are in place.

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.r------------------------------------------U------------------U l

l EFFECTIVE PROGRAM Determine That No Program is l

l EVALUATION Required, Create New Program, j

l or Modify Existing Program for l

Components Which Have ARD UTLR l

i

__s e_ _ ____ _______,________________________--

_ :___________=--

s

h"EI((fl.(1Y Examole 6 - Instrument Cable to RPS Pressure Transmitter inside Containment: Provide Signal

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System ITLR Function:

Trip reactor on high RCS pressure.

Component ITLR Function: Provide a pressure signal to the RPS while in a harsh environment.

1. Can component ITLR function be assured with performance-based program?

1.A Not active.

1.B.1 Failure causes only one channel to be lost, system can still function.

1.B.2 Failure not revealed (cable not subjected to design basis conditions during normal operations or testing).

Answer is NO

3. Component covered by commodity report for instrument cables in containment.

Action:

Utility verify that commodity report applies and that effective age-management programs are in place.

.m

B&WOG GLRP IPA PROCESS

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__=_____________

o_____.______--____o___N_o_____________________--______________--

i l EFFECTIVE PROGRAM Determine That No Program is EVALUATION Required. Create New Program, l

l or Modify Existing Program for l

l Components Which Have ARD UTLR l

L________________________________-____-__-________________________________________--______________--

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Example 7 - RPS Reactor Trio Module. Channel A: Generate Trio Sional PRE.,,MTV RY System ITLR Function:

Trip reactor under unsafe operating conditions.

Component ITLR Function: Initiate a channel reactor trip signal when trip conditions are met.

1. Can component ITLR function be assured with performance-based program?

1.A Function is Active Answer is YES

2. Existing performance-based program effective?

2.A Failure detected by periodic surveillance test (Tech. Spec.)

2.B MR programs monitor RPS performance 2.C Specific criteria for surveillance testing and repetitive failure are defined in MR performance criteria.

Procedure requires corrective action when limit reached.

Answer is YES Action:

Document program bases.

P DRAFT B&W OWNERS GROUP GENERIC LICENSE RENEWAL PROGRAM INTEGRATED PLANT ASSESSMENT COMPONENT SCREENING METHODOLOGY i

r B&W Nuclear Technologies Duke Power Company Entergy operations, Inc.

Florida Power Corporation GPU Nuclear Corporation Toledo Edison company a

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l April 9,1993 Figure 1 GLRP COMPONENT SCREENTNG METHODOLOGY 4

un or m.R ssCs 5

and their ITLR Functims l

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Dom Component l

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No Accomplishment of i

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System / Structure i

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...............................7.....................................................;

l sectim 3.2 l

l Detennine m.R Compments I

and their ITLR Functims l

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Which Support MLR j

Sysem / Structure Functions e

i i

i e........................................................................................i.

s i

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l Sectim 3.3 l

l Documentatim l

l Ust of ITLR Components l

j l

A their ITLR Functims

!i 4

i i

1 6....................................................................

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1 1

1

..cv ce System / Structure Screening Methodology Document, Section 3.4.

System / Structure Screening Methodology Document, Section 5

3.3.

i Page 2

1 l

-CRITERIA 1.

THE COMPONENT IS REQUIRED TO FUNCTION FOR THE ACHIEVEMENT OF A SYSTEM / STRUCTURE ITLR FUNCTION.

92.

2.

IF THE COMPONENT WERE TO Fall (IN ANY MODE),

THE FAILURE WOULD CAUSE EITHER OF THE FOLLOWING CONDITIONS TO BE SATISFIED:

1 a.

A PARTIAL OR COMPLETE LOSS OF A SYSTEM / STRUCTURE ITLR FUNCTION, OR b.

A PARTIAL OR COMPLETE LOSS OF THE STRUCTURAL SUPPORT OF AN ITLR PORTION OF A SYSTEM.

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ANO-1 SCREENING BASIS DOCUMENT DRAFT

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98.

Reactor Building Heating and Ventilation (RBHV)

G Safety-related function to reduce post-accident RB pressure and temperature by transferring heat from the RB atmosphere to service water.

(ULD-1-SYS-06) 2)

Safety-related function to provide post-accident mixing of the RB atmosphere. (ULD-1-SYS-06) 3)

Safety-related function to provide containment isolation of penetrations that do not serve any accident-consequence-limiting system function.

(ULD-0-TOP-14) 4)

Contains electrical equipment relied upon to meet NRC regulations for environmental qualification,10 CFR 50.49. (ULD-0-TOP 01) 5)

Emergency cooling portions of this system are subject to Technical Specification LCOs 3.3.1(B),3.3.4(A), and 3.3.7(C) and (D).

i

SCSCREEN.XLS COMP. ID l COMP. DESCRIPTION l COMP. FUNCTION l SYS. ITLR FUNC. SUPPORTED VSF-1 D BLOWER PRESS _URE BOUNDARY RBHV-1,2&S FLU _ID FLOW RBHV-1,2&S MOT _R MOTIVE POWER RBHV-1,2,4&5 O

VCC-2D HEAT EXCHANGER PRESSURE BOUNDARY RBHV-1,2&S

{_

TRANSFER HEAT RBHV-1 C203 ELEC. CABINET STRUCTURAL INTEGRITY RBHV-1,2&5 B52_44 CIRC _UIT BREAKER OPEN ON CIRCUIT FAILURE RB_HV-1 &2 CV-7404 VALVE PRESSURE BOUNDARY RBHV-3 STROKE CLOSED RBHV-3 VAL _VE OPERATOR CLOSE VALVE R_BHV-3 M_O_ TOR MOTIVE POWER RBHV-3 CV-7473 DAMPER PRESSURE BOUNDARY RBHV-1,2&S STROKE OPEN RBHV-1,2&S I

[ DAMPER OPERATOR OPEN DAMPER RBHV-1,2,4&5 MOTOR MOTIVE POVER RBHV-1,2,4&5 HVD-69 DAMPER PRESSURE BOUNDARY RBHV-1,2&S HS-7413 HAND _S_ WITCH

'D_O_NOT FAIL CIRCUlT R_BHV-1&2 SV-7413 DAMPER PF: ESSURE BOUNDARY RBHV-1,2&S STROKE _O_PE_N R_BHV-1,2&S DAMPER OPERATOR OPEN DAMPER RBHV-1,2,4 & 5 MOTOR MOTIVE POWER RBHV-1,2,4&5 ZS-7413 SWITCH (POSITION)

DO NOT Fall CIRCUIT RBHV-1,2&4 PSV-7421 VALVE PRESSURE RELIEF RBHV-1&2 42X5185 RELAY ENERGlZE CIRCUlT RBHV-3 N/A DUCTWORK(1)

PRESSURE BOUNDARY RBHV 1,2&S N/A PIPE (2)

PRESSURE BOUNDARY RBHV-3 c

N/A CABL5(3)

CARRY CURRENT RBHV-1,2,4&5 NOTES:

(1) INCLUDES ALL DUCTWORK NOT ASSOCIATED WITH VSF-1E.

(2) INCLUDES RB PENETRATION PIPING ONLY (V1&V2).

(3) INCLUDES ALL CABLE ASSOCIATED WITH VSF-1 A-D,SV-7410-I 7413,CV-7470-7473,& CV-7401-7404 ONLY, i

Page1

f 3

ULD-1-SYS-OG REACTOR BUILDING HVAC/ PURGE ATTACHMENT 1/PAGE 3 OF 4 l

CRDM SHROUD EL 401 RB BASEMENT RV CAVITY A,

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A SUPPLY PLENUM 1

1 1

CV-7470

/ CV-7472 J-CV-7471 --

CV-7473 --

VSF-1 A VSF-1 B VSF-1 C VSF-1 D w

V V

V V

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V V

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  • During accident conditions air bypasses VCC-1 A thru D and enters directly into the VCC-2A thru D Cervice Wator Coils REACTOR BUILDING COOLERS - AIR FLOW

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SYSTEM SCREENING METHODOLOGY

)

SCOPE OF METHODOLOGY HIGH LEVEL FUNCTIONAL TEST CONSIDERS EACH PLANT's CLB SITE IMPLEMENTATION PROVIDE RESULTS FROM SEVERAL PLANTS INCLUDE SYSTEM FUNCTIONS IN SUBMITTAL NOT FSAR CHAPTER ENCOURAGE SITE VISITS (EARLY JUNE)

RAI RESOLUTION CONTAINED IN AN APPENDIX WRITTEN RESPONSE BY MAY 19

)

SCHEDULE FOLLOW-UP MEETING i

l

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