ML20154D076

Summary of 880424 Info Exchange Meeting W/Nuplex Technical Subcommittee,Doe,Epri & Natl Labs in Rockville,Md.Viewgraphs & List of Attendees Encl

ML20154D076
Person / Time
Issue date:	04/29/1988
From:	Vora J NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Vagins M NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
NUDOCS 8805190037
Download: ML20154D076 (43)

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APR 2 0 1988 MEPORANDUM FOR:

Milton Vagins, Chief Electrical and Mechanical Engineering Branch Division of Engineering, RES J. P. Vora "' W'cha'nical Engineering Branch FROM:

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SUBJECT:

NUPLEX TECHNICAL SUBCOMMITTLE MEETING 1

An open information exchange meeting was held at 5650 Nicholson Lane on March 24, 1988 between the NRC staff and the rep osentatives of NUPLEX technical subcommittee, DOE, EPRI, and national ioboratories. The meeting was attended by approximately 30 people. The meeting agenda includin; the names, affiliations, and phone numbers of those in attendance, are attached for your information.

(Enclosures 1 and 2).

The first part of the meeting was spent discussing the screening methodology (Enclosure 3) developed by the Sy(dia National Laboratory. The purpose of the methodology, from the industry perspective, is to develop a systematic approach for identifying the scope of equipment to be considered for life extension.

This generated quite a bit of discussion regarding the criteria used by Sandia for selecting the systems and components. The attached vu-graphs of this portion of the meeting describe the screening process in detail.

In the afternoon, Ed Shomaker discussed the ways, conforming to the NRC requirements u lines, to review the technical reports generated by the EPRI, DOE, and and gu e

the ii. astry sponsored research programs. A brief discussion followed on the i

EPRI proprietary reports (EPRI NP 518M, SP) on nuclear plant life extension (Enclosure 4).

NUPLEX presented an executive summary (Enclosure 5) of their program plan.

They would like to see a stable, timely license renewal process. They are also coordinating the utility PLEX efforts. An interesting development is that NUMARC is also establishing a Comittee on plant aging and life extension within the next few weeks.

As the result of this, NUPLEX has to get NUMARC's approval on their activities, so this may,affechtheir milestones and schedules.

Mr. Karl Kniel of NRC's Office of Nuclear Regulatory Research presented a status report on NRC license renewal activity. Mr. Kniel discussed NRC's rationale for not developing a policy statement ori license renewal and instead proceeding to develop a rule.

The main reason is that NRC would like to save n;ne and come out with a rule as soon as possible. Mr. Kniel expects to send tne rule to the Commission in the 1990 to 1991 time frame.

Industry is not too 8805190037 880429 RES SUBJ

2_

happy about waiting another three years to get an idea about what to expect in the license renewal process.

NUPLEX stated that they expect to havc couple of "volunteer" lead plants by next year. They worry that with all the uncertainties and lack of clear guidance from NRC, the lead plants and the industry as a whole will be very reluctant to spend their resources and begin the process.

They strongly encouraged NRC to provide them with some "broad" guidelir es as soon as possible. The most pressing of all the issues to the industry is the licensing basis.

Karl Kniel and other NRC staff involved were very pleased with this open discussion. Apparently, this was the first time that NRC had becorre aware of what the indust.y is looking for as far guidance from NRC to proceed with their life extensior activities.

9()%k ora Electrical and Mechanical Engineering Branch Division of Engineering, RES

Enclosure:

As stated cc:

R. Bosnak (w/o enclosures)

PDR(withenclosures)

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' l' FEETING - NRC/NUPLEX TECHNICAL SUBCOMMiiTEE Place:

U.S.N.R.C.

Date: Thursday, March 24, 1980 l':00 a.m. - 4:00 p.m.

5650 Nicholson Lane Time:

0 Rockville, MD Conference Room 013 AGENDA 10:00 a.m.

Opening Remarks R. Bosnak - NRC L. DelGeorge - NUPLEX 10:15 a.m.

Screening Criteria D. Carlson - SANDIA t

12:00 LUNCH 1:00 p.m.

Handling of Technical Reports R. Bosnak/E. Shomaker - NRC (Reference NUPLEX Letter Dated 3/7/88) 1:30 p.m.

Executive Summary - NUPLEX Plan L. Del George - NUPLEX 2:00 p.m.

NRC/NPAR Comparison L.-Del George - NUPLEX 2:30 p.m.

Industry Reports - Update o BWR RPV J. Chardos - NUPLEX o PWR Containment P. Beament - NUPLEX 3:00 p.m.

Status Report on License Karl Kniel - NRC Renewal Related Activities 3:30 p.m.

General Discussion - Administrative

- ALL l

4:00 p.m.

Adjourn

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i NcLosuRC 3 SCREENING METHODOLOGY:

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MARCH 24,1988 l

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DAVID D. CARLSON i

DOE TECHNOLOGY MANAGEMENT CENTER 1

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CURRENT STATUS i

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UNDERGOING TECHNICAL REVIEW i

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1 DEVELOP A SYSTEMATIC APPROACH FOR DEFINING THE SCOPE OF EQUIPMENT TO

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WHICH SET OF PLANT EQUIPMENT SHOULD BE SUBJECT TO NRC REVIEW FOR

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LICENSE RENEWAL I

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LICENSE RENEWAL SHOULD FOCUS ON ENSURING CONTINUED SAFE OPERATION l

FOR THE LICENSE RENEWAL PERIOD AS SUCH, UCENSE RENEWAL SHOULD RECOGNIZE THAT SOME OY9TEMS PLAY A MORE iMPORTANT ROLE IN CONTINUED SAFE OPERATION FURTHERMORE, SOME COMPONENTS ARE MORE SIGNIFICANT TO l

PERFORMING THE SYSTEPa'S SAFETY FUNCTIONS LICENSE RENEWAL SHOULD TAKE INTO ACCOUNT THE EXISTING TEST, l

MAINTENANCE, AND SURVEILLANCE PROGRAMS WHICH ASSURE THAT SAFETY MARGINS ARE PROTECTED BOTH DETERMINISTIC AND PROBABILISTIC APPROACHES EXIST FOR IDENTIFYING AND EVALUATING THE SIGNIFICANCE OF AGE-RELATED DEGRADATION i

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FIGURE 1; A Methodology to Determine Portions of the Plant Subject to License Renewal Review q

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INITIAL APPLICATIONS OF SCREENING METHODOLOGY FOR PURPOSES OF NUPLEX:

I IDENTIFY. INITIAL LIST OF BWR AND PWR "SYSTEMS SUBJECT TO LICENSE RENEWAL REVIEW" "COMPONENTS IMPORTANT TO LICENSE RENEWAL" AND EVALUATION I

OF POTENTIAL SIGNIFICANCE OF AGE-RELATED DEGRADATION FOR j

EXAMPLE HPCI (BWR) AND AFW (PWR) SYSTEMS l

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TABLE 1: PREllMINARY SET OF BWR SYSTEMS SUBJECT TO LICENSE RENEWAL REVIEW NUCLEAR BOILER SYSTEM REACTOR RECIRCULATION SYSTEM CONTROL ROD DRIVE SYSTEM STANDBY LIQUID CONTROL SYSTEM REACTOR PROTECTION SYSTEM RESIDUAL HEAT REMOVAL SYSTEM CORE SPRAY SYSTEM HIGH PRESSURE COOLANT INJECTION SYSTEM REACTOR CORE ISOI.ATION COOLING SYSTEM CONTROL ROOM RHR SERVICE WATER SYSTEM ISOLATION CONDENSER lNSTRUMENT PNEUMATIC SYSTEM DIESEL GENERATOR SYSTEM (INCLUDING EMERGENCY AC POWER)

PRIMARY CONTAINMENT STANDBY GAS TREATMENT SYSTEM EMERGENCY EQUIPMENT COOLING EMERGENCY HVAC DC POWER SYSTEM CLASS I CONCRETE STRUCTURES HYDROGEN CONTROL SYSTEM FIRE PROTECTION SYSTEM AUTOMATIC DEPRESSURIZATION FEEDWATER COOLANT INJECTION SYSTEM

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SIGNIFICANT AGE-RELATED DEGRADATION i

IDENTIFY DEGRADATION MECHANISMS j

ASSESS QUALITATIVE EFFECTS j

PROBABILISTIC BOUNDING (CHANGE CORE DAMAGE FREQUENCY BY237)

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INITIAL COMPONENT LIST 287 195 i

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REPLACEMENT, REFURBISHMENT, INSPECTION 108 15

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COMPONENTS WITH POTENTIALLY SIGNIFICANT AGE-RELATED DEGRADATION 2

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PWR AFWS:

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PUMP TURBINE ASSEMBLY (INCLUDES PUMP DRIVE l

TURBINE, AUXILIARY OIL PUMP, GLAND SEAL CONDENSER, i

CONDENSATE PUMP, LUBE OIL COOLER, STEAM SUPPLY STEAM TRAP)

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FOCUS FURTHER BASED ON QUALITATIVE ARGUMENTS PROBAB!LISTIC ARGUMENTS COULD FURTHER FOCUS ON SYSTEM l

INVESTIGATION (SEE SURRY PRIORITIZATION) i WITHIN SYSTEMS, SELECTED COMPONENTS IMPORTANT FOR SAFETV i

FUNCTION OF THESE, MANY ARE PART OF EXISTING REPLACEMENT, REFURBISHMENT, INSPECTION PROGRAMS FOCUSES ATTENTION ON SELECT FEW WITH POTENTIAL FOR AGE-RELATED DEGRADATION WHICH COULD IMPACT SAFETY PROFILE OF SYSTEMS EVALUATION VARIES FROM SYSTEM TO SYSTEM, PLANT i TO PLANT l

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INITIAL _ PLANT-SPECIFIC EXAMPLE SYSTEMS _

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PRIORITIZE SYSTEMS FOR CLOSER EXAMINATION i

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i INITIAL PROBABILISTIC SCREENING OF SURRY SYSTEMS i

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HIGH AUXILIARY FEEDWATER SYSTEM (INCLUDING CONDENSATE STORAGE) 1 l

CONTAINMENT

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G. Neils NSP; Chairman NUPLEX STEERING CONIMITTEE

< e 12) 337-2003 Nuclear Utility Plant Life Extension D. Hostetler, Virginia Power:

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'/ ice Chairman (804)775 5083 I

March 7, 1988.

Mr. Robert J. Bosnak U.S. Nuclear Regulatory Commission Washington, D.C.

20553

Subject:

SPRI PROPRIETARY REPORTS ON NUCLEAR PLANT LIFE EXTENSION i

Dear Mr. Bosnak:

As you are aware, the EPRI reports documenting the Monticello Pilot Plant Life Extension Phase 1 study ('JPRI NP5181M, SP) previously provided to 'you are considered proprietary by EPRI and should be returned to:

Dr. John J. Carey Electric Power Research Institute 3412 Hillview Avenue Palo Alto, California 94303 In order to make these repc,rts and other proprietary reports developed by EPRI in the area af Nuclear Plant Life Extension, available to NRC staff and their contractors, a 'teading rcom' has been established at the EPRI Washingto,n D.C.

Office, where these reports can be reviewed.

The ' reading room' currently contains the Monticello Life 2xtension reports referred to above and the Surry

.j Unit-1 Pilot Plant Life Extension Phase I study report (EPRI NPS289P).

NRC staff and their contractors can make arrangements to review these reports by contacting:

Mr. Jack Berga EPRI Washington DC Office l

Suite 1000 1019 19th Street, hN Washington, D.C.

20036 (202) 872-9222 i

I appreciate your ccoperation in this matter..

Sincerely, e

EA Gerald H. Neils NUPLF.X Chairman t

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D. iostetler j

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l NUPLEX PROGRAM PLAN EXECUTIVE

SUMMARY

A PRESENTATION TO NRC BY NUPLEX TECHNICAL SUBCOMMITTEE L. DEL GEORGE, Chairman MARCH 24,1988 i

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i OVERALL PROGRAM OBJE.CTIVES 1.

PROMOTE A STABLE, TIMELY LICENSE RENEWAL PROCESS 2.

COORDINATE UTILITY PLEX EFFORTS

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NUPLEX PROGRAM STRATEGY THE NUPLEX PROGRAM IS BASED UPON CURRENT KNOWLEDGE ON LIFE EXTENSION, LICENSE RENEWAL, AND UTILITY MANAGEMENT NEEDS.

THE PROGRAM STRATEGY HAS THREE ASPECTS:

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e NUPLEX PROGRAM PRECEPTS PRECEPT 1 - CONTINUUM. LIFE EXTENSION SHOULD REQUIRE CONTINUATION OF THE ESTABLISHED PERFORMANCE, RELIABlUTY, AND SAFETY REQUIREMENTS FROM THE CURRENT LICENSE TERM INTO THE EXTENDED TERM.

EBE_QEPT 2-APPROVED LICENSING BASIS. THE APPROVED LICENSING BASIS IN EFFECT AT EACH NUCLEAR POWER PLANT ON THE DATE OF RENEWAL APPLICATION SHOULD BE THE STANDARD USED IN THE RENEWAL PROCESS TO JUDGE SAFETY DURING THE EXTENDED TERM.

PRECEPT 3 - LICENSE REN!!WAL DEALS WITH A KNOWN ENTITY.

FOR LICENSE RENEWAL, OPERATIONS ARE KNOWN OVER THE PLANT OPERATING PERIOD. THIS PERFORMANCE OVER TIME (l.E., THE PLANT OPERATING HISTORY) CAN AID IN A LICENSE RENEWAL REVIEW.

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1 NUPLEX PRODUCTS METHODOLOGIES AND DATA RESOURCES SCREENING METHODOLOGIES INDUSTRY REPORTS OPERATIONS DATA BASES POSITION PAPERS PETITIONS FOR RULEMAKING DRAFT CODES & STANDARDS COMMENTS ON PROPOSED CHANGES TO REGULATIONS AND REGULATORY GUIDES LICENSING TOPICAL REPORTS j

1 r

NUPLEX PROGRAM ELEMENTS:

WORK BREAKDOWN STRUCTURE NUPLEX HAS ORGANIZED ITS FUNCTIONS AND RESPONSIBILITIES AMONG FOUR SEPARATE PROGRAM ELEMENTS:

COORDINATION TECHNICAL LICENSING CODES & STANDARDS i

EACH PROGRAM ELEMENT HAS AN AGENDA CF SUBELEMENTS AND TASKS THAT IMPLEMENT THE NUPLEX PROGRAM STRATEGY.

I

NUPLEX STEERING COMMITTEE COORDINATION ACTIVITIES WORK BREAKDOWN STRUCTURE 3

Program Element A NUPLEX Steering Committee Coordination Subelement A.1 Subelement A.2 Subelement A.3 Subelement A.4 l

Program Lead Economic Technology Integration Plants Evaluations Transfer

I b

NUPLEX TECHNICAL SUBCOMMI I I l-E WORK BREAKDOWN STRUCTURE 4

Program Element B r

Technical i

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Subelement B.1 Subelement B.2 Subelement B.3 I

l Research Needs Decision-making industry Report j

Tools & Data Tasks l

Resources l-i I

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Plant Systems ir Significant Yes Safety No Not a to Bafety NUPLEX' or Economics' issue f

if r

l Yes - Economics (only)

Prepare R

Report

+

,r Info Industry industry Review Review Exchange Process

+-- with NRC t

1r l

Need for Position Paper i

Licensing Code & Standard l

i l

DEVELOPMENT OF INDUSTRY REPORTS j

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1 J

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Overall Plant 43.em level Screenin for Safety and Economic Im 4

+

Safety Non. Safety i

Significant Significant Systems Systems Component Level Screening for System Performance Yes No Imonet

+

+

r E xisting Not Significant Significant Impact on System Licensing to System m

Basis Performance Performance I

Age Related Degradation l

Screening for impact on Component o formane e

\\

Yes

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Significant Not Significant impact on System to System Pedormece Pedormance i

'P Methodology for Life Assessment Components Addressed by De:Jgn 4

Basis Plant Maintenance L

Acceptance Programs 4

Criteria r

CMes &

Standards Assessment t

j h

k Generic Plant Unique Components Components Life Assessments Life Assessments t

+

Prodletive Mitigative Preventative Corrective Actions Actions Actions Actions j

IR DEVELOPMENT PROCESS i

NUPLEX LICENSING SUBCOMMITTEE WORK BREAKDOWN STRUCTURE 3

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Program Element C Licensing i

1 I

q 4

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Subelement C.1 Subelement C.2 Subelement C.3 Subelement C.4 i

j Policy Working Regulation Environment Special Studies Group Working Group Working Group Working Group i

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NUPLEX CODES AND STANDARDS SUBCOMMITTEE WORK BREAKDOWN STRUCTdRE Program Element D Codes and Standards 1

Subelement D.1 Subelement D.2 Subelement D.3 Monitor Codes and Liaison Central File Standards Committees &

with NUPLEX Technical and Documentation of Working Grou-and Licensing Activities Codes and Stand.ards e

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