ML20057A842
| ML20057A842 | |
| Person / Time | |
|---|---|
| Issue date: | 08/27/1993 |
| From: | David Nelson Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9309160015 | |
| Download: ML20057A842 (16) | |
Text
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- ~N UNITED STATES E~
.E NUCLEAR REGULATORY COMMISSION 8
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August 27, 1993 FACILITY: Nuclear Management and Resources Council (NUMARC)
SUBJECT:
SUMMARY
OF MEETING WITH NUMARC WORKING GROUP ON LICENSE RENEWAL CONCERNING INDUSTRY ACTIVITIES ASSOCIATED WITH LICENSE RENEWAL On Friday, August 13, 1993, representatives of the NUMARC Working Group on License Renewal met with the NRC staff to provide a status briefing on efforts to develop an industry consensus approach to license renewal. is the meeting attendance list. is a copy of information provided by NUMARC for discussion during the meeting.
NUMARC has formed a License Renewal Implementation Ad Hoc Advisory Committee (LRIAHAC) comprised of representatives of owners groups, utilities, vendors, the Electric Power Research Institute and the Department of Energy.
The committee is developing a new industry approach for Integrated Plant Assessments (IPA) for screening systems, structures, and components (SSCs) important to license renewal (ITLR). NUMARC emphasized the validity of the two fundamental principles of license renewal and expressed a desire for maximum reliance on existing licensee programs and activities for managing age-related degradation.
Licensees will use an IPA like framework to screen SSCs ITLR for age-related degradation unique to license renewal (ARDUTLR) based on preservation of system and component function and will maximize reliance on existing programs to manage ARDUTLR in the renewal term. Members of the LRIAHAC will apply the draft approach to their specific programs on a trial basis and will use the results of the trial applications to revise the proposed industry approach, as necessary.
The staff and NUMARC discussed the draft approach in some detail.
The staff asked questions regarding several topics including:
submittals for review of new or enhanced technical programs needed to manage aging, plans for modifying existing programs such that an applicant can conclude aging is not UTLR, basis for controls on programs, and the decision process for selection of what to review.
In response to staff questions, NUMARC indicated that a number of significant issues have not yet been addressed. NUMARC expressed a desire to provide further staff briefings on the refined approach and stated further 150012 g,, (pggp)
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August-27, 1993 Meeting Summary of August 13, 1993 '
details would be included in their presentation at the planned public workshop. The staff stated that alternative approaches are welcome and described the public workshop scheduled for September 30, 1993, as an appropriate forum for further presentations.
Original signed by:
David J. Nelson, Project Manager License Renewal and Environmental Review Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosures:
1.
Attendance List 2.
NUMARC Handout DJSTRIBUTION:
Central File PDR PDLR R/F TMurley/FMiraglia,12G18 JPartlow, 12G18 DCrutchfield, llH21 WTravers, llH21 SNewberry, llF23 FAkstulewicz, llF23 DNelson,11F23 LLuther, llF23 OGC EJordan, MNBB3701 ACRS (10)
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DOCUMENT NAME:
NELSON MEETING
SUMMARY
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ENCLOSURE 1 AUGUST 13. 1993. ATTENDANCE LIST MEETING WITH NUMARC NAME ORIGANIZATION Steve Reynolds NRC/NRR William Travers NRC/NRR Don Eggett BWROG Ray Ng NUMARC Deborah Staudinger BWOG John Giddens WOG Les England BWROG Kathryn Kalowsky Winston & Strawn Tricia Heroux EPRI Kris Shembarger NRC/0CM Karen Cyr NRC/0CG Annette Vietti-Cook NRC/0CM Harold Polk NRC/NRR Chong Lewe NUS Sam Lee NRC/NRR Debbie Jackson NRC/NRR P. T. Kuo NRC/NRR T. Tai Bechtel A. Pfeffer Bechtel Ted Meyer WOG Bob Borsum BWNT Jim Raleigh STS Inc.
Paul Shemanski NRC/NRR Raj Anand NRC/NRR Dave Nelson NRC/NRR Anthony Gody, Jr.
NRC/EDO Rebecca Nease NRC/NRR Eileen McKenna NRC/0CM Richard Correia NRC/NRR Jeff Sharkey NRC/NRR Fred Burke BWNT C. A. Negin Grove Engineering Geary Mizunno NRC/0GC Frank Akstulewicz NRC/NRR Scott Newberry NRC/NRR Marty Malsch NRC/0GC Barth Doroshuk BG&E Ellen Ginsberg NUMARC David Lewis Shaw Pittman John Moulton NRC/NRR P
P
ENCLOSURE 2 NRC/ INDUSTRY MEETING 1
ON LICENSE RENEWAL AUGUST 13,1993 ROCKVILLE, MARYLAND 1
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PROPOSED AGENDA Introc uction f
Industry IPA approach
- Concepts
- Flow diagram
- BG&E test example Summary
- Current Status
- Future activities NUMARC 1
LRIAHAC MEMBERSHIP BG&E NSP B&WOG BWROG WOG EPRI DOE NSSS Vencors NUMARC 2
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LRIAHAC. ACTIVITIES 10 meetings since May 1993 Technical assessment o' regulatory issues 1
License renewal technical evaluation
-IPA-li<e framework
- Flow ciagram
- Narrative guidance L
NuMARC i
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INDUSTRY IPA CONCEPTS L
r Two funcamental princiales o" license renewal Reliance on existing activities anc programs Emphasis on.lTLR function Technical demonstration
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54.21 (a) SSCs ITLR Industry Approach 54.21 (a)(1) & 54 21 (a)(2) n
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'I6s the SC been evaluated to yes renewal term and the evaluation p
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'N SC does not have No ARDUTLR 3
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.fian the performance of the SC Yes l
No 4
1I Identify ARD for each SC Y
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Do the effects change in character or Yes magnitude
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Does the mechanism only occur in the Yes newal term *
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y SC is subject to SC does not have A DUM ARDUTLR
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DRAFT 1
NUMARC LICENSE RENEWAL IMPLEMENTATION AHAC PROPOSED INTEGRATED PLANT ASSESSMENT PROCESS 1.
SSCs ITLR AND FUNCTIONAL SCREENING The screening criteria for SSCs "important to license renewal" (ITLR) are provided explicitly by 10 CFR 54.3.
From the list of SSCs generated in 54.21(a)(1) perform screening for ITLR functions pursuant to the requirements of 10 CFR 54.21(a)(2).
2.
HAS THE SC BEEN EVALUATED FOR THE RENEWAL PERIOD AND THE EVALUATION FOUND ACCEPTABLE BY NRC There may be SCs important to license renewal that are already evaluated for the period of extended operation and the evaluation found acceptable to NRC. If these evaluations resulted in a determination that the SC will perform its intended function in the renewal term then no further action is necessary and the disposition of the SC in the LR application is that it is not subject to age-related degradation unique to license renewal (ARDUTLR)
Similarly, an applicant may elect to included an evaluation of the SC (for the renewal period) in the renewal application. In this situation [it is assumed that if the NRC accepts the analysis] the SC is predisposed as not having ARDUTLR. If the NRC does not accept the analysis, the applicant must then analyze the SC in accordance with the remaining steps of the IPA process.
3.
CAN PERFORMANCE OF SC FUNCTION BE ASSURED?
1 This step is intended to take credit for existing programs which assure that ITLR SC functions are assured. Examples of existing programs include:
Replacement and refurbishment programs, based on time or condition, o
which reasonably assure that the SC function is preserved.
o Maintenance rule activities, which include corrective actions, that provide reasonable assurance that system performance is maintained abdve a specified performance criteria.
DRAFT Periodic testing and inspection programs which verify functional o
performance, and which include corrective actions to restore functional performance, Diagnostic and monitoring programs, which include corrective actions, o
intended to trend equipment performance.
CLB programs which assure SC functionality.
o If an existing program is identified which assures the ITLR function, then the SC does not have ARDUTLR. If no such existing program can be identified, the SC is passed to the following steps for disposition.
4.
IDENT]FY SC ARD Age-related degradation mechanisms and/or effects are identified for each SC ITLR. The choice of either mechanism or effect is made for each SC based on the approach to be used to disposition the item.
5.
EFFECTS DIFFERENT IN CHARACTER OR MAGNITUDE?
If any identified degradation has effects which satisfy this criteria, the SC is explicitly considered to have ARDUTLR.
The character of degradation is different when either the rate of degradation for the period of extended operation increases significantly from that expected such that the degradation would result in unacceptable performance or condition of a structure of component (i.e., outside the current licensing basis) during the period of extended operation or if the physical or chemical properties of a material or component change from the expected behavior to tlw extent that a limit of the current licensing basis is exceeded.
Effects of degradation that are different in magnitude refer to the condition that occurs when degradation of a structure or component (1) continues beyond the degradation that would have occurred if operation had ceased at the end of the current licensing term, and (2) the degradation would result in unacceptable performance or condition of the structure or component (i.e., outside the current licensing basis) during the period of extended operation.
i 2
August 12,1993
l DRAFT 6.
DEGRADATION ONLY OCCURS DURI'NG RENEWAL TERM 7 This question corresponds to the third part of the ARDUTLR definition. If any degradation for a particular SC satisfies this criteria, that SC is explicitly considered to have ARDUTLR.
The effects of degradation that " occur only during the period of extended operation" are degradation effects that manifest themselves only during the period of extended operation and whose effects would result in unacceptable performance of condition of the structure or component (i.e., outside the current licensing basis).
7.
SC SUBJECT TO ARDUTLR Any SC having degradation satisfying the queries about " character and magnitude" or "only during the renewal term" parts of tLe ARDUTLR definition, is considered to be subject to ARDUTLR.
8.
SC DOES NOT HAVE ARDUTLR If performance ofITLR functions is assured by existing programs, or if the SCs performance / function has been previously evaluated for the renewal term, and the evaluation accepted by NRC concluding no ARDUTLR, or if such an evaluation is provided as part of the LR application, or if the degradation does not satisfy any aspects of the ARDUTLR definition, then the SC does not have ARDUTLR.
9.
EFFECTIVE PROGRAM REQUIRED?
This logic is derived from 10 CFR 54.21(a)(5), to allow the conclusion that an j
" effective program" is not required.
1 This step permits the deliberate choice of a program which might not completely satisfy the requirements for an " effective program," but which adequately mitigates the effects of ARDUTLR. Altematives include such things as a one-time j
action (e.g., single inspection), component modification or replacement, or analysis.
3 August 12,1993
DRAFT 10.
DOCUMENT BASIS This step provides documentation of why an " effective program" is not required, and may include a discussion of any alternative actions.
I1.
DOCUMENT AND IMPLEMENT This step documents that the recommended program is: (a) adequate to manage the aging degradation, and (b) consistent with the " effective programs" criteria provided in 10 CFR 54.21(a)(6).
4 August 12,1993
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SUMMARY
OF RESULTS BGE IPA NUMARCIPA PROCESS PROCESS No. of Adequate Existing Category Components Programs UTLR Programs UTLR l
l Steam Generator 4
0 l
4 4
l 0
Mechanical 135 16 119
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24 Valves 633 87 546 518 115 I&C 1235 1235 0
1235 0
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RCP &
Pzr Htrs 295 279 l
16 279 l
16 l
l TOTAL 2302 1617 155 685 2147
a
SUMMARY
Sept. '93 Detailec industry IPA Sept. '93 NRC workshop participation Fall '93 Technical cemonstration
- B&WOG i
-BG&E
-BWROG NUMARC 5
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