ML20215L024

Plan for Integrating Technical Activities within the U.S. NRC and ITS Contractors in the Area of Thermal Hydraulics

ML20215L024
Person / Time
Issue date:	04/30/1987
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
NUREG-1244, NUDOCS 8705120074
Download: ML20215L024 (42)

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NUREG-1244 Plan for Integrating Technical Activities Within the U.S. NRC and Its Contractors in the Are'a of Thermal Hydraulics U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research pa arco q fI ihg$/

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NUREG-1244 R4 1

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Plan for Integrating Technical ,

Activities Within the U.S. NRC and Its Contractors in the Area of Thermal Hydraulics i

Manuscript Completed: March 1987 Date Published: April 1987 Division of Reactor System Safety i Office of Nuclear Regulatory Research l U.S. Nuclear Regulatory Commission Washington, DC 20555

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. ABSTRACT The Executive Director for Operations (EDO) directed the NRC staff to prepare

-a coordinated plan for the integration of technical activities within the-agency and specified a number of issues to.be addressed. This report suninarizes the status of agency programs involved in themal hydraulic research and proposes management methods .to accomplish the ED0's directives.

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CONTENTS Page

1. Introduction and Sunnary 1 II. Current Status arid hethods for Achieving Technical Integration 4

1. Definition of Major Program Objectives 4

2. Responsibilities and Interrelationships of Different NRC Offices 6

5. Coordinaticn and Establishment of A.gency Objectives S

4. Coordination with U.S. Industry 10

5. International Cooperation in Themal Hydraulics 11 III. Integration of Thermal Hydraulics 12

1. Introduction 12

2. Regulatory Resoarch Review Group 13

3. Thermal Hydraulic Research Program Plan 19

4. NRC Contractor Operated Technical Integration Center for Thermal Hydraulics 19

5. Topical Summaries of Research Results 25

6. Revision of Policy and Planning Guidance .(NUREG-0885) 25

7. Performar.ce Evaluations 25

8. Periodic Briefings of EDO, Consission, and ACRS 26 IV. Schedule and Budget Requirements for Technical Integration 27 V. Acknowledgement 27

'II . References 27 Appendix A: Draft Charter for Regulatory Research Review Group for Thermal Hydraulic Activities A-1 Appendix B: FY 1987 Program P.rief for Themal Hydraulic Technical Integration Center B-1 Appendix C: Current Performance Appraisal Elements Which Deal With Technical Integration C-1 y

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1. Introduction and Summary The Executive Director for Operations- bas directed the NRC staff to prepare a i coordinated plan for integrhtion of technical activities within the agency.

In addition he directed that the plan addresses the issues in Table 1 as well as changes which are necessary to facilitate technical integration.

This report reviews the current status and propcses certain raanagement methods i to enhance thermal hydraulic technical integratien within the different FRC

Offices and among NPC contractors. Implementation of this plan will require l further refinement by the parties involved. Chapter 11 contains a descr5p- >

! tion of the current working methods and relationships. Chapter III prov_, des reconnendation designeo to achieve improved technical integration. Chapter IV discusses schedule and budget requiren:ents. The 10 issues in Table 1 are addressed in this plan, but are not specifically enumerated due to the considerable overlap and close relationship of the irdividual items. Regarding i the last of these points, NRR and PES staff are ccruitted. to eliminating and

reducing costs through the identification of duplicative. efforts.

A plan is presented for improving technical integration within the NRC, princi-pally between NPR and RES, for regulatory issues whose effective resolution 4 involves thermal hydraulics. Specitic reconvendations are maos to irrprove and accelerate the integration of research results into the regulatory process that-include a Regulatory Research Review Group and sumary reports on completed  ;

research. To assure that the present exercise remains functional in the future l suggestions are made for coverage of thermal hydrauiic technical integration in

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the Policy and Planning Guidance Report (hbREG-0E85), incorporation of a tech-nical integration critical elment inte performance appraisals for appropriate staff, and periodic briefings of the EDC, the Commission, and the ACRS on thennal hydraulic technical integration. Included is a discussion of how a

. Technical Integration Center can as;ist the hFC staff.in achieving effective technical integration and closure of issues. The process for consolidating

research projects into a Technical Integration Center is also discussed and

specific recommendations are made.

i While thermal hydraulic phenomena pervade the entire range of reactor sequences from normal operation through severe accidents, this plan is concerned mainly with accident mitigation and ptevention of core melt. It thcludes the thermal

. hydraulics of light water reactors from steady state operation up to the initi-

! ation of significcht core darrage. Integration of. severe accidents is not ad-dressed in this plan since the dominant phenonwna are different. As relevant thennal hydraulic issues are identified through the severe accident program, i however, they could be includea in the integration plan.

This plan was prepared assuming that the organizational structure in place at the beginning of CY 1967 would be utilized. While the reorganization which wiii occur in April 1987 will alter the membership of some groups ~ and sone

, organizational interactions, the basic concepts and procedures presented ir.

l this plan will be unchanged.

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TABLE 1

1. Definition of major program objectives and discussions of how they-are .

conducted among all offices / regions.

2. Methods for establishing and maintaining inter-office coordination and

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communications.

3. Identification of lead and support responsibility.

4. Ways to factor previcus related agency experience into programs.

5. Methods for regular review of programmatic status by lead and supporting office / regions.

6. Discussion of a mechanism to identify and use state-of-the-art experience and inferwation from other government, industry, and foreign sources and to disseminate this information interoclly and to relevant contractors.

7. Discussion of provisions for effectivt utilization of research results and responsibtlities for assessing regulatory significance of centractor-progr6ms.

6. Discussiens of ways to facilitate cccperation and communications among j contractors.

9. Discussion of the use of " lead contractor approach" for integrating technical results and providing reconTeendations regarding applicability of results.

10. Describe the attentien given to eliminate duplication cf effort. l l

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This plan addresses the types of therral hydraulic transients that are normally considered in the regulatory process of licensirg the current generation of light water reactors. This process is influenced by the reSulatory requirerents imposed by the NRC and the consequent need f or technical  ;

information that is provided by RES thrcugh its contractors. Thus, most-  !

contractor programmatic work is aoministered by RES. Regulatory requirements invcive the normal review of industry analyses nf design basis accidents, as well as the understandir.g of abnormal occurrences in operating reactors such as have occurred in TMI-2, Davis-Besse, Ginna, and Rancho Secc. Since transients of this type often involve complex thermal hycroulic interactions, h well planned and integrated thermal hydraulic resee.rch plan is needed.

The relationships and respcnsibilities of offices within the f;RC for thermal

, hydraulics can be summarizeo as follows. The lead role in defining issues and objectives and performing technical review is provided by fiRR. Much of the technical basis and the analytical tools for decisions involving thermal hy-draulics is suppliec by RES, which has the statutory authority and responsibil-ity to develop recenmendations for, engage in, and contract for research deemed necessary for performance of NRC's licensing ar.d regulatory function. Compli-ance is monitored by I&E. AE0D, which is independent of the routine regulatory process, identifies issues for review based on plant operational data.

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II. Current Status and Methods for Achieving Technical Integration in Thermal Fydraulics

1. Definition of Major Program Objec,tives lhe NRC has the responsibil ny to assure that nuclear power plants are de-signed, constructeo, and operated in a tranner which is consistent with protecting tre health and safety of the public. The hRC operates according to the principle that safety of plant design, construction, and. operation is the responsibility of the licensee. Nevertheless, the NRC (principally NRR) must have the ability to independently judge plant designs and safety analyses submitted by licensees and license applicants. Further, NRC (principally IAE and regional offices) must have the ability to deterwine that plants are built and operated in conformance with applications for construction permits, licenses for operation, technical specifications, and the Code of Federal Regulations.

Since NRR, I&E, and AECD must have the capability to review operating experience, NRC staff pust obtain a sound understonding of the important physical phenomena that ney occur during transients in operating power plants.

The specific fur.ctions the NRC staff performs in the area of thermal hydraulics are listed below with the principal responsible office:

Confirn safety margin in licensee analyses by performino audit calcu-lations (NRR);

Investigate and resolve safety issues, e.g. , ATWS, pressurized ther-mal shock, feed and bleed, etc. (NRR, RES);

- Evaluate the impact of design and operational related changes (NRR, I&E);

- Evaluate plant Technical Specifications, including safety limits and limiting conditions for operation (FRR);

Develop and validate analytical models (RES);

Develop or modify regulatory standards (RES, NRR)

Examine the adequacy cf cperator guidelines (hRR);

lJnoerstand operating reactor transient events and their implications (NRR,AE0D,ISE,RES);

Communicate operating and inspection experience to the industry via information notices (IAE);

Promulgate bulletins requiring licensees to submit information and take remedial action, where appropriate (I&E);

1 Verify and validate probabilistic safety studies, e.g., success cri- '

teria, accident sequence models, and effect of operator actions (NRR, RES);

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- Answer questions from licensing boards, the Consrission, Congressional Constittees, and the public (NRP, PES, IAE, AE00); and

- Provide inforroation on the early phases of postulated severe accident sequences (RES).

In practice, perfoming these functions requires the ability to urterstand and describe the processes of heat transfer and fluid flow in light water reactors for the range of plant transients that may occur. This includes the design 4 basis accidents requirea to be analyzed in license applications and reviewed by i NRR, as well as other transients beyond the design basis that tray be postulated 1 for the different plant designs in operation, under construction, or proposed in the United States.

Design basis accidents consist of an initiating event such as a failure of an active (pump or valve) or passive (pipe break) component plus additional, but limited failures. The rules and guidance for the analysis of design basis events by applicants and their review by NRR are contained in 10 CFR 50, the standard review plan (NUREG-0800), and various regulatory guides and standards.

Examples include Final Safety Analysis Report Chapter 15 scenarios such as

- Increase in heat removal by the secondary system (steam line break, steamger.eratoroverfeed);

- Decrease in heat removal by the secondary system (loss of feedwater.

stationblackout);

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- Decrease in reactor coolant system flow rate (reactor coolant puttp trip);

- Reactivity ar.d power distribution er.cmalies (boron dilution, rod withdrawal);

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- Increase in reactor coolant inventory; and

- Decrease in reactor coolant inventory (LOCA);

In addition to design basis events, some combinations of multiple failures and/or operator errors need to be considered. The credibility of such scenarios is established through probabilistic safety studies and through actual operating experience. Significani operational transients have occurred at Rancho Seco, Davis Besse, Arkansas Nuclear One, Three Mile Island, Ginna, Salem, and elsewhere.

FFC uses research results, operating experience, and other infomation to assess the safety of plant design and operation. Technical aspects of these evaluations often require technical assistance contracts. Such contracts make use of contractor expertise developed by NRC-spensored research.

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2. Responsibilitics end Interrelationships, of Different NRC Offices The main interfaces between the NRC Offices are surmarized as follows: .

NRR - The Office of huclear Reactor Regulation (NRR) has the principal responsibility for determining the safety of nuclear power plants. NRR is the primary user of thermal hydraulic information and provides a principal i

influence on research objectives ard priorities. NRR generates much of its own' required information and obtains information through technical assistance programs and through vendors and licensees via topical reports and responses to infomation requests. If NRR decides that.new research information is needed in the fom of a computer code, modifications to a code, or experin+ntal data, the Director of NRR will request.that RES

develop and provide the necessary information. Then, RES has the responsibility for providing validated codes and experipental data to assure this validation. NRR considers conclusions from AE00 studies in formulating research needs and priorities.

. The principal products that NRR uses are experimental data, ccsputer codes, t

and results of ccde analyses. The codes nedel plant behavior by describ-ing the processes of heat transfer and fluid flow that occur in a plant,

! and predict the plant response to disturbances from nomal operating conditions. A principal requirement, therefore, is for assessed computer codes that are sufficiently accurate for the purposes for which they are -

used. In addition, NRR requires that a sound physical understanding be obtained of the important phenomena that may occur during transients in i i operating power plants and for specific safety issues. '

l When urgent regulatory issues arise, NRR analyzes and assesses these is- ,

i sues. Frequently, technical assistance resources are employed to assist  !

in this effort. If needed, NRR requests assistance from RES and its con- '

j tractors to do follow-on studies after the initial urgency has passed.

NRR funds its own technical assistance work, while RES funds follow-on work requested by NRR plus any additional research deemed necessary.

, RES - The Reactor Systems Branch of RES is responsible for planning and l carrying ct.t the thermal hydraulic research necessary to obtain the infor-i mation requireo by NPR. RES performs research (utilizing contractors) according to technical need established by RES staff and in response to NRR requests and ACiis recommendations. . RES plans research with NRR advice and concurrence. The research is conducted with the assistance of the.

responsible NRC contractcr.

l. Resultant information must be summarized and transferred to NRR in such a manner as to be readily usable in decision-FMking ano the regulatory pro- 1 i cess. RES holds periodic meetings with its contractors to review progress -l ano pit.n future work. Results are documented in periodic' research  !

reports, in summary reports at the conclusion of major milestones or the end of the project, ano in research information letters (RIls).

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1 The purpose of research is to procuce the information necessary for the NkC to respond to regulatory issues affecting the design, operation, ano maintenance of nuclear power plants. The principal products,of research

are experimental data and computer codes to understand and predict the plant response to disturbances from nonnal operating conditions.. RE5 pro-vides shpport to NRR for first-titre use of the codes to new regulatory -

issues. NRR then applies the codes, es required, for subsequent analyses. ,

l The Severe Accident Sequence Analysis (SASA) program uses thennal hydraulic and other computer codes to calculate ceteministic consequences of the risk dominant secuences. The Pisk Analysis Branch perfoms

] probabilistic safety studies utilizing computer codes and the physical '

'- understancing aeveloped through thermal hydraulic .research. Such studies provide a method of cataloging and arranging in order of significance, the accident sequences representing important threats to the fuel, the reactor coolant system, or the containment. The research results assist hkR in i

evaluating industry risk assessment studies. This risk assessment

perspective coupled with thermal-hydraulic information provides insights

.l on safety issues related to plant design, plant diagnoses for incident

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response and cperator action, and procedures based on symptets observed.

! These insights are fed back when determining priorities for thermal i bydraulic research and when screening plant systems for data collection j needs.

AE0D - The Office of Analysis and Evaluation of Operating Data is respon-sibTe for the detailed analysis of operating experience. This includes plant-specific and general implications of-operating transients. The thermal hydraulic respcnse of the plant is frequently a key facet of

operating transients. The major issues defined by AEOD investigations will influence the research plan. Conclusions from AEOD studies are considered by NRR in formulating research needs ano priorities.

I&E - The Ottice of Inspection and Enforcement and the Regional Offices are responsible for' ensuring that nuclear power plants are constructed,-

operated, and maintained in accordance with NRC regulations. As

, necessary, I&E is in direct contact around the clock with control rooms at 3

operating nuclear power plants through the NRC Operations Center.

l Licensees are obligated per the regulations to report certain kinds of i events to the Duty Officer in the Operations Center by telephone.- Thus, ,

! significant themal hydraulic transients are reported promptly to the  !

Resident Inspector and to the Operations Center.- Each normal working day,

' all events reported by telephone to the Operationis Center and in the ,

! regional daily reports are screened jointly by T&E and FRR in a conference  !

! call and follow-up action is agreed upen. Such actions may include l reccrimendations to perform research, where appropriate.

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l 1&E is responsible for training PRC personnel to respond in the Operations.

r Center to accidents at nuclear power plants. I&E interacts with RES through the use of plant analyzers in planning and conducting training ex-ercises for response teams. IAE would also make use of the Plant Data Bank in the Operations Center if it were available.

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l I&E is responsible for development of the independent treasurements program to evaluate purformance of nuclear power plants in selected areas. For example, I&E has produced computer software to determine reactor power levels for_ sore types of plants by dcir.g a heat balance on the reactor coolant system.

IP - The Office of International Programs is responsible for concluding "iilternational agreemehr.s on exchange of research and regulatory information.

IRM - The Office of Information and Resource Managenent has developed an uniform policy concerning distribution of new NRC codes and has set standaros for their docuirentation.

OGC - The Office of the General Counsel is consulted as required concerning contracter or international affairs. OGC is consulted by NRR on licensing issues, which are only infrequently related to thermal hydraulics.

EDO -(Incident Investigation Teams) Operating transients invariably in-ciude some combination of multiple equipment malfunctions, operator er-rors, ir. appropriate procedures, or inadequate training. Such transients often require a coordinated response from I&E, NRR, and AE00. When impor-tant transients occur, the EDO forms incident investigation teams to eval-uate the incident in detail and report. Davis-Besse and Rancho Seco are recent examples.

3. Coordination and Establishment of Agency 0,bjectives General agency objectives and policy are established and presented in the annu-al Policy and Planning Guidance Report (NUREG-0885). Subjects covered in this report such as operating reactor licensing actions, design basis accident re-views, unresolved safety issues, improved and advanced reactor designs, severe accidents, assessment of operating reactor events, and improved regulation, are isnpacted by our understanding of thermal hydraulic phenomena.

NRR has lead responsibility for implerienting and determining agency objectives in the area of thennal hydraulics. RES is the main support office in obtaining information necessary to meet these objectives. The specific program for NPR implementation of the Folicy and Planning Guidance is contained in the NRR operating plan, which specifically states that NRR is responsible for the performance of safety reviews for construction permits and cperating licenses.

NRR also ensures that nuclear plants achieve and maintain adequate levels of health and safety protection. This is accomplished by reviewing and acting upon numerous actions Lssociated with operating power plants.

The research aspects of Policy and Planning Guidance are implementeri in the annual Long-Range Research Plan (NUREG-1080). This plan is additionally formu-lated through technical need established by RES, NRR user requests, and ACRS connents. Also, input is received from the NRC Lt.dget Review Crcup and the Senior Contract Review Board. RES programs are regularly reviewed by the ACRS l

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and its subconnittees. The ACRS prepares an annual report to Cor,gress and the Commissict on the hRC research program. RES annually prepares and updates the Long-Range Research Plan which defines and justifies the major regulatory needs, and describes a research plan that is intended to meet these needs. The thermal hydraulics section of the plan includes four elements: (1) separate effects experiments end n.odel development, (2) integral systems experiments, (3) code assessment and applicatier, and (4) plant analyzer and data bank.

Each year the Lcng-Range Research Plan is updatec by RES. Fregrams are gener-ally defined in response to NRR requests and NRR follows the research results.

NRR reviews the plan to ensure that the research program meets their needs and dces not duplicate NRR technical assistance work. NRR comments are formally submitted to RES. The plan is also distributeo to other NRC offices, EDO, ACRS, and the Cor.nission for review. Folicwing publication, the report is dis-tributed outside the NRC.

Inadvertent duplication of research efforts with other government, industry, or international research is avoideo by appropriate planning by RES project manag-4 ers, by information exchange with groups sponsoring research in and outside the U.S., and by conducting literature surveys and planning by the RES contractors.

Interoffice duplication is avoided by NRR reviews of RES prcjects as part of the annual review of the Lcng-Range Research Plan. This review ensures that NRR technical assistance programs do not replicate research programs. As part of this review, FRR also checks that RES programs do not ouplicate each other, or other industry research. Coordination on an international basis is performed through hilateral agreements end through the International Code Assessn.ent and Applications Program. Experience has not shown duplication to be a problem.

When NRR decides that particular research is needed, a user need letter is for-mulated. Prior to issuance of a formal letter, information needs are discussed between RES and FER at the working level. The user need letter is typically addressed from the Director of NRR to the Director of RES. Research plans are formulated in response to user need requests consistent with availtble resourc-es. Communication is maintained between the responsible Branch Chiefs or Divi-sion Directors through routine meetings and telephone conversations.

Modifications may be made, as required, to research in progress.

The above, normal methods for systematic program definition become altered dur-ing periods of budget reductions, as has been conmon durir.g the past several years. At such times, RES must make quick decisions, based on pre-planned cri-teria, regarding programmatic reductions without the normal consultative process with NRR and ACRS. NRR may not have an oppertunity to influence decisions that are made. On such occasiens, subsequent disagreements are ,

avoided through prior agreement on research priorities. A formal procedure )

that would allow swif t censultations between hER and RES would be of benefit. i l

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hhile care is normally taken not to duplicate efforts, sometimes additional research is purposely undertaken Lc repeat or' refine past research.. Experi-ments may be performed using better . instrumentation io achieve better data, or to check results that seem ambi t uous or uncertain. Additionally, where avail-able modeling is insufficient to meet regulatory needs _and the best approach is not clear, parallel approaches may be tollowed. Such was-the casc'until re-cently with the development of two PWR codes, TRAC-PWR, and RELAP5.

Research results are normally transmitted to NRR and other user offices as a series of technical reports. On occasion, contractors.have issued sumary re-ports of scmewhat broader scope, but often.still limited tc experiments per-formed in a single tacility. RES has grcuped conclusions fretc related research

r. subject areas and transmitted these results together with recomenc'ed ac-tions to user offices via Research Information Letters (RILs). Generally, how-l ever, RES has not published reports which prcvide comprehensive discussions of all relevant information cr. a given issue and previce a resolution.

The RFS staff is responsible for assessing and ir.tegrating the results of indi-vidual contractor efforts. RES and NRR share primary responsibility for inte-(, rating resuits into the regulatory process: RES by working with NRR on.the fomulation of revised rules and standards; and NRR by making use of technical

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infornetion developed by research. RES staff is also responsible for ensuring-that coordination is maintained between contractors perfoming parts _of an overall project.

Althcugh presently functioning with soire degree of success, the tasks of coor-dination and integration between hRR, RES, and contractors can be improved.-

Suggested methods for doing so are the subject of Section Ill.  ;

4. , Coordination with U.S,._Indu::try, Where appropriate, the NRC cooperates with U.S. industry in carrying out re-search programs. The establishment et joint prcgrams.is:normally sought as a raeans of sharing the costs involved and in broadening the technical. input to- ..

given projects. The industry groups most often -ir.volved are the Electric power; Research Institute (EPRI), the NSSS vendors and utility owners groups. A cur-rent example of such cooperation is the Multi-Loop Integral System Test (MIST).

program, which is sponsored by the NRC, EPPI, B&W, and the B&W Owner's Group.

The MIST program is managed by a program management group consisting of _ repre-sentatives of each of the parties involved. Similar past examples include FIST, FLECHT, TRAC-BWR, and COBRA-TF.

In general, the NRC research staff taintains contact with inoustry representa-tives or thermal hydraulic projects. The industry representatives recene prograr reports and are invited to research information meetings. =In the 2D/3D project, for example, the vendors normally attend the regular n.eetings and -

comp +nt on the plan of work and ar.41yses of results. Such comments are considered by RES in defining the experiment specifications and plan. The NRC also sponsors the . annual Water Reactor Safety Infomation Peeting that includes safety research results from NRC contractors, U.S. industry, and foreign institutiens.

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4 Much thermal hydraulic work of interest to NRC has been performeo by EPRI and the ver. dors. NRC receives all EFril thermal hydraulic reports and has periodic meetings to coordinate research plans and discuss research programs of mutual i interest. NRR also receives information directly from the vendors and

licensees via license applications, responses to requests for information, and topical reports. RES intends to continue research collabcration with industry whenever common objectives are identified and agreement can be obtained on the conduct of joint programs.

! 5. International Cooperation in Thern.a1 H.ydrau,1,1cs, s The NRC research staff places importance on cooperation with other countries in

, the area of thermal hydraulic research. Such cocperation can be bilateral or multilateral. The hRC has negotiated bilateral thermal hydraulic exchange agreements with nearly all noncommunist block countries with nuclear power programs. The most inportant of these include France, Federal Republ_ic of Germany, Italy, Japan, Sweden, and the United Kingdom. These agreements form the basis of the International Code Assessment Program (ICAP). Under this program, the NRC has provideo its advanced, best-estimate thermal hydraulic codes TRAC-PWR, RELAPS, and TRAC-BWR in exchange for assessment and appli-

cations information and experimental data. The NRC serves as coordinator of this joint-international project on the quantitative assessment of NRC codes.

The ICAP program takes in essentially all major nuclear thermal hydraulic experimental facilities in the world.

The trilateral 2D/3D program between the NRC, Federal Republic of Gemany and Japan is a Joint project investigating large-break loss-of-ccolant accidents.

The OECD LOFT Project is a program of experiments in the LOFT facility. The project has 10 member nations, and the U.S. membership includes the NRC, EPRI, anc 00E. These projects are governed by boards consisting of representatives from each member.

The NRC participates in the Committee on the Safety of huclear Installations (CSNI) of the OECD Nuclear Energy Agency. Within CSNI the subject of thermal hydraulics is covered by the Principal Working Group 2 on Transients and Breaks. This group provides a forum for multilateral discussien and information exchange. It also provides a method for carrying out international standard problem exercises. The current membership of this group includes a single principal representative from NRR. Information is distributed to interested NRC staff and contractors through trip reports. In addition, IP receives all CSNI documents.

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t III. Intecration of Thermal Fydraulics

1. Introduction The following presents methods for improving integration pertaining to thermal hydraulics. These methods are intended to supplement rather than replace existing arrangements. The changes include: (1) hRR/RES regulatory research i review group (RRRG); (2) thermal hydraulic research program plan; (3) NRC '

contractor operated technical integration center for thermal hydraulics; (4) topical summaries of research results and associated code assessment; (5)revisionofthe-policyandplanningguidancereport(NUREG-0885);

(6) revisions to performance evaluations; and (7) periodic briefings of the EDO, the Commission and the ACRS on thermal hydraulic technical Artegration.

This section discusses these seven changes, the first four of which are based on a memo from the Director of fiRR (Reference 1).

The procedure followed by the NRC staff for thermal hydraulic issue resolution will-be as follows, L

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- Identify and prioritire the regulatory objectives or safety issues  !

and establish the specific RES-NRR coordination required, as well as 1 l

coordination with other offices, as appropriate. Assure that specific tests, analyses and reports are associated with specific l

regulatory issues or regulatory objectives. Assure that RES is kept 1 informeo of regulatory issues and cbjectives. (RRRG)

! - With the assistance of an NRC contractor, identify existing informa-

! tion available from domestic and foreign sources, assess the total

research support needed, and formulate research program and schedule.

(RES,RRRC, Contractor)

- Assure that the NRR group using the research is also the group approving its initiation, continuation, and conclusions. Assure that continuity of purpose ano objectives is maintained, with allowance for new safety issues or priorities baseo on operating experience.

(NRR)

- Contract for any needeo research. (RES)

I - Monitor technical progress and schedule; integrate relevant informa-j tioncontractor.

the by including RES, (results ano conclusions of relar.ed research through Contractor)

- Assure that the research is technically sound and that progress is

( being made toward achievisig the stated objectives. Provide for peer l review cf research results. (RES,RRRG)

- Summarize and disseminate results of completed research to NRR and other users. Regulatory integration is to be an explicit part of every research program. Provide summary tcpical reports when com-pleted research achieves closure on re ulatory issues.or objectives and transmit to NRR. (RES, Contractor 12

I i - Incorporate the results in the regulatory process, including revising rules and regulatory guides where appropriate. (NRR,RES,RRRG)

- Periodically review with ALRS the regulatory objectives or safety issues, technical progress, research results, and incorporation of information into the regulatory process. (RES,NRR)

I

2. Regulatory Research Review Group i 1

A NRR/RES Regulatory Research Review Group (RRRG) is being established to l assist in defining and prioritizing issues requiring resolution and to review '

research progress with a view to transferring information in forms.that are readily usable to NRR. Membership on the RRRG will be jointly determined by the office directors concerned.- The group will te the main method for enhan-cing interoffice communications and for regular review of progransnatic status.

The purpose of the RRRG is to proacte technical integration of research into

! the regulatory process and Ic assure joint accountability in achieving closure on issues. This differs from current research review meetings between RES and its contractors which focus on details of experimentation and analysis. Much of the discussicn is from the viewpoint of specializeo research experts rather than the regulator. The pFRG will concentrate on the definition and resolution of iss9es to ensure that research is focused on the needs of the principal user -

office (NRR). A draft charter of the RRRG for thennal hydraulics is provided in Appendix A.

In addition, the RRRG will provide an opportunity for NRR and RES to discuss priorities. In current situation, progres that are in place to cbtain

research information specifically requested by NRR a

ay be severely curtailed cue to budget reductions. This immediately gives rise to concerns over priorities with respect to all RES sponsored thermal hydraulic research. The RRRG will form reconeendations for reordering of priorities. If satisfactory

agreenent cannot be reached in the RRRG or if upper RES and NRR management do not agree with the RRRG conclusion, then the office directors of the two offices will resolve the differences. The RRRG will also review and provide recommendations on significant code development and assessirent work. Examples of issues and and projects designed to address them are contained in Tatle 2.

The RRRG will participate with ADM and IRM in the review of adequacy of agency

( guidance on code maintenance and documentation.

l l 'Ihe RRRG will regularly report to Office Directors Of RES and NRR as to whether

! the scope of research and technical assistance G M 'ects are appropriately fo-l cused and time schedules are adequate to set W y t e needs of the regulatory l program. The grcup will provide recommenia! vis 4 the office directors on reordering of priorities oue to budget coerc.derans.

The RRRG will include several members from RES and NRR and will be chairod by the Deputy Director, Division of Safety Review and Oversight. Representatives from the thermal hydraulics technical integration center will attend meetings in a consulting capacity. Adaitional a*.tendance will be based on the subject i matter of the meeting. Representatives of ISE, AE00, or cther NRC staff will  !

be invited whenever appropriate, as well as technical consultants, as needed.

l Regularly scheduled meetings will be held no more frequently thar quarterly.

Ad hoc meetings will be held as required in response to urgent issues.

13

TABt2 2 yng PROJECT (FIN 5) RES REGULATORY FIST & rtST/UBS SEMISCALE/ CEC ROSA- 20/30 ICAP DOM- TRAC- TRAC- RA- NPA/ NPA SEPARATE T.I.C. A-47 A-45 ISSUE MB-2 IV ASSESS NBL ESL MONA 08 SNL EFFECTS (SG-TR) STUDIES STUDIES (SEC0Y MEAT ggp$ -1118 RE90 VAL)

, A6039 38909 A2026 A6038 A6843 A6340 A6100 85537 A7312 A3374 A7016 A6052 A3014 A6342 A3227 Univ. Other M3%

A7311 A7248 A6400 G1043 A6363 80413 A7C49 A6827 A7307 Labs . A6328 A7281 A7202 Core uncovery in PWR's due to 5.G.

Ilquid hold-up a m x x x Steam emplosions =

l Iodine transport after SGTR x x ,

System behavfor after SGTR x x x x x x Steam binding in PWR's x Alternate ECC concepts x x x x x

$ PWR plant re-covery tech-niques a m x x x x 5.G. heat transfer under accident condt-tions x x x x x 4

ECCS rule eevt-slon x x a a a u a x 1

. Decay heat x x R R N removal X .. x i

t 1

~ .

TABLE 2(continued)

PROJECT (FINS) RES 20/30 ICAP DOM- TRAC- TRAC- RA- urA/ NPA SEPARATE T.I.C.

REGULATORY FIST & MIST /tNe SENISCALE/ CEC ROSA-ASSESS Pun sua MONA 33 BNL EFFECTS ISSUE pe-2 IV

( assars -111a A3227 Univ. Other M 354 A6039 88909 A2026 A6038 A6843 A6340 A6100 85537 A7312 AI374 A7016 A6052 A3014 A6342 A7311 A7248 Labs A6328 80413 A7049 A6827 A7307 A6400 G1043 Feed & bleed ca-l pability of 84W , x Plants x l

Instrument tube x x x

failures x 58LOCA & N.C.

(Baw); TMI-Issues x x x x x Water hammer UPI capability u", (w 2-Ioop) x x x x BE LDCA pheno-mena in PWR's x x x x ECC bypass x

(PWR's)

Fluid / fluid six-ing in DMDut x x

(PTS)

Soron mixing in x 8WR's

L 6 TABLE 2 (continued)

PROJECT (FINS) -RES REGULATORY ' FIST & MIST /UMD SEMISCALE/ CEC ROSA- 20/3D ICAP 00M- TRAC- TRAC- RA ' NPA/ NPA SEFARATE T.I.C.

ISSUE se-2 IV AS. FWR BWR MONA 08 BNL EFFECTS SSESS RELAPS 1118 i

A6039 B8909 A2026 A6038 A6643 A6340 A6100 85537 A7312 A1347 A7016 A6052- A3014 A634; A3227 Univ.~ --Other A6354 '

A7311 A7248 A6400 G1043 80413 A7049 A6827 A3215 A730 Labs A6328 58LOCA w/o WI x x x x F/S line breaks .x x x x Influence of .

control systee on course of events x x x x x. x 4

r i

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TABLE 2(continued) l - NRR

, PG0 JECT (FIN 5) #E5 l

' 4:A 4'CES 7151 & NIST/UBS SEntSCALE/ CEC a05A- 20/30 ICAP 00M- TaAC- TRAC- RA- NPA/ NPA SEPAAATE T. I .C. DECK MPA REVIEW 5 BNL

'KIIIYI 88-2 IV AS- IWt BR Mona 08 Out EFFECTS DEVELOP- 18FLEIE NT-l 55E55 IEIAP5 -tale 'Euf ATION l "

A7272 i

A6039 30909 A2026 A6038 A6443 A6340 A6100 85537 . A7312 Al374 A7016 A6052 A3014 A6342 A3227 Univ. Other M3% A6002 A3M '

i A6003 A7207 A1314 A37N A7311 47240 l

- A6400 G1043 00413 A7049 A6427 A7307 Labs M328 A6013 '06006 Alsos A37N Scsting of data 43 fs11-scale tWE's a- a a a a a a a m Quanti fIcat ten tf code uncer-tataty a a a a Storage of plant data for needed analyses 8 "

leproving cape-

- bility of Slack fos training sfe-slaup 3 E I Spector slaula-I ties for op.

( center drills a a leprovements in rundamental code a a a a a R E endelling User friendly R M " ' '

camputer codes i

O l

t l-l

=

b

ji .

1 In addition- to the RRRG, the current research review and program management meetings between RES and its contractors continue as before. NRR will cer.tinue

- to designate cognizant individuals who serve as the lead technical ~ persons for i NRR on particular research programs.

2

3. Thermal Hydraulic Research Program Plan

. The function of the program plan is to present a greater level of detail than is available in the Long-Range Research Plan so that the research plan and ob-jectives can be better understood and evaluated by the offices concerned. The plan is being prepared by RES with input from NRR and will be updated annually.

It will:

! - Define the major issues the NRC is seeking to resolve and provide plans for their resolution;

- Relate the proposed research to these issues; i

- Define the products needed to resolve these issues;

! - Provide a context that shows a historical perspective and the rela-

! tion of individual projects to the overall objectives; and -

i

- Define major interfaces with other disciplines, e.g. structural, j severe accident) needed for total resolution of the issue.

The thermal hydraulic research program plan is currently being prepared.

Table 2 shows a list of regulatory issues and objectives, and RES and NRR pro-grams'under which they are being addressed. IAE and AE0D do net have signifi-i cant contractor programmatic efforts in these areas. hER projects, shown on l the right of the table, are restricted to input deck development, NPA implemen-tation, industry reviews, audit calculations, and studies related to unresolved safety issues A-45 and A-47.

4 NRC Contractor Operated Technical Integration Center for Thermal Hydraulics The technical integration center is responsible for maintaining overall cogni-zance in the area of thermal hydraulics, regardless of the sources of information. None of the duties associated with the technical integration center and primary thermal hydraulics contractor in any way diminish or replace the regulatory or research responsibilities of the NRC staff. Rather, it en-sures that contractor expertise remains available to the NRC staff. This expertise is utilized to enhance the integration of research results into the regulatory process and to maintain a pool of knowledgeable staff to respond to NRR needs and regulatory issues.

.l 19

I Interface responsibilities for the technical integration center tre as follows:

Chief, Reactor Systems Branch, RES Group Manager, Reactor Thermal Hydraulics, INEL.

Reductions in the NRC research budget have resulted in sharp decreases in the funding for thermal hydraulics. It is no longer possible to support the pro- ,

grams formerly in progress at a number of different laboratories. The staffing i and support levels at several organizations where NRC formerly supported sig- i i nificant research efforts have fallen below minimum " critical mass" levels

! needed to perform work requiring group expertise. Remaining resources, an im-portant part of which is the expertise developed from past NRC research, must be carefully conserved.

i l A significant portion of the remaining thermal hydraulic research and technical assistance work is being consolidated at INEL, which serves both as lead con-tractor and technical integration center. INEL has historically been the major contractor for thermal hydraulics, has acquired significant expertise in exper-

imental programs and code development, and has the largest. remaining staff of 1 thermal hydraulic experts. RES, however, maintains expertise at more than one

! laboratory sufficient to avoid potential conflict of interest problems associ-q ated with technical assistance programs and to assure technical diversity. It

is RES policy to er.phasize ' university programs .as a primary method of maintain-ing independent expertise, j Certain thernal hydraulic work continues to b'e performed at other DOE laborato-J ries or organizations in those cases where expertise which is superior to that j of the technical integration center exists or as part of a joint project with ,

J EPPI, the vendors, or with other governmental or . international agencies. Uni- '

! versity programs are an important part of these efforts. For such work, the i technical integration center maintains cognizance, including the possible as-i signment of resider.t engineers to major projects. Upon completion of the re-search at these other organizations, the products.of the research, e.g., codes and data, are transferred to the technical integration center to assure integration. Liaison could be improved between INEL and NRC by assigning i respective staff (NRC at INEL or INEL at NRC) for extended periods of time to assist with specific projects devoted to resolving regulatory issues. Table 3 shows a list of projects and where they are being performed.

INEL assists the hKC in providing integration in thermal hydraulics by carrying

out activities-at the direction of the NRC in the following areas

Identify existing information available and assist the NRC in formulating research programs and schedules; l

Providing syntheses of completed research to assist in incorporating research results into the regulatory prccess; Maintaining cognizance of research being perforned or having been performed by other hRC contractors, industry, and foreign courtries; l l

20

__ .-. _ _ _ - , _ _ _ _ _ _ _ _ _ ___ _ .___ _ _ _ . . _ D

_ , . . ~. _ . _ _ _ - - - - _ _ _ _

Table 3. LIST OF RESEARCH PROJECTS Projects at INEL Cocperative Programs Support (FIST and MS-2) (A6030)

MIST Instrument Facility Support (A6400) 20/3D Instrumentation and Resident Engineer (A6100)

I:05A-IV Support - Instrumentation and Resident Engineer (A6363)

ROSA-IV Data Analysis (shared with LANL) (A6340)

Continuing Experimental Capability (A6343)

DAE Data Bank (A6102)

ICAP Progran and User Support - TRAC-BWR and RELAP5 (A6827)

Code Improvement and Maintenance - TRAC-BWR, RELAP5, and COBRA (A6052)

Nuclear Plant Analyzer Executive (A6342)

Themal Hydraulic TIC (A6328)

GTSG Separate Effects Tests (A6855)

Prcjects at LANL MIST Analysis (A7311)

ROSA-IV Data Analysis (A7248)

TFJC Applications to 2D/3D (A7049)

TRAC-PWR Code Development (A7016)

ICAFProgramandUserSupport-TRAC-PWR(A7312)

Nuclear Plant Analyzer and Data Bank (A7307)

Projects at Other National Laboratories Modeling of Two Phase Flow (A2026): Argonne National Laboratory TRAC-BWR Assessment (A1347): Brookhaven National Laboratory Code Maintenance - RAMONA-IIIB (A3014): Brookhaven National Laboratory Code Assessment and Applications (A3215)

EkF Plant Analy:er (A3227): Brookhaven National Laboratory Critical Flow Through Pipe Cracks (B3043): Lawrence Berkeley Laboratory Advanced Instrumentation for PWR Reflood Studies (B0413): ORNL Steam Generator Tube Rupture (B0832): ORNL ThTF Maintenance (80463): ORNL TRAC-PWRAssessment(A1374): Sandia National Laboratory

ncustry Cooperative Programs MIfT Facility (B8909): Babcock and Wilcox l'r.iversity Procrams Rixin'g in Etratified Flows (D1634): University of California Sarta Barbara {

Ur.iversity of Maryland Loop (D1639): University of Maryland Kater Hamer (61099): Massachusetts Institute of Technology Small Business Programs LCCN ECCS Support Studies (B5537): MPR 21

~

• Maintaining computer codes, quer.tifying the code accuracy _with respect to regulatory issues and objectives,' assessir.c code scaling capability, and assessing the effects of any code shortcomings and identifying any compensating errors (i.e., getting the right answer for the wrong reason);

• Providing rapid technical response as requested by hEF to urgent regulatory issues raised as a result of transients in operating power '

i plants such as Davis-Besse, implications for feed and bleed in

Babcock and Wilcox plants, and consequences of instrument tube fail-i ures in Westinghouse plants; i

• Providing support for special'. studies and projects such as technical l

basis for proposed ECCS rule revision and improving capabilities of NRC Black Fox training simulator;

!

• Provide options and reconsnendations for future research requirements

! with respect to: technical basis for NRC audit of industry requests concerning improving plant capacity factors, improving technical i specifications, and improving plant design and safety systems; evalu-ating effects of design differences between nonstandardized plant designs; and achieving better operator training, better operator pro-l cedures, and better diagnostic aids; i

I

• Susunarizing and integrating results from different programs or tasks, discussing their significance, and providing recomunendations regarding their applicability to the regulatory program; and l

• Deconstrate effectiveness of a multidisciplinary research approach to issue resolution. ,

f

! The products of research programs have nomally consisted of numerous individu-al contractor reports providing results of individual portions of'the overall

! program. These reports are aimed at documenting research results as opposed to j presenting information in a form that can be readily incorporated into the reg-

! ulatory process or be used to address the resolution of the particular issue

that originally motivated the research. There is a need, therefore, for-

. summary reports that integrate and assess the significance of individual l reports and answer the original concerns. Such reports should lead to staff positions on issues.

I Thermal hydraulic research has generated a large amount of information. The-need to synthesize and implement research results is apparent in view of the

resource exper.ditures being allocated to thermal hydraulics, currently about

560M per year internationally and $1400M total to date. Most of this informa-

! tion resides in large nuir.bers of progranwatic reports. Almost all currently planned research will be completed by about 1990, while nuclear power is ex-i pected to cor.tinue much longer, even if new plants are not built. The existing research infomation nust be documented in forms 'that can be readily retained and utilized in the lon5 term or else much of it wiil be effectively lost.

The selection cf topical surcaries will be made on an issue basis and identified by the RRRG.

22

The main fccus of the technical integration center is the establishnent of val-idated analytical tools used by the NRC for the evaluation of LWR safety. A second goel is to put in place mechanisms to permit the rapid dtployment of personnel and resources to address safety issues related to thernal hydraulics as they arise. A guiding principle is rendering the products of research (i.e.,

codes, data, methods) more usable in the regulatory framework, that is, synthesizing research results so that they are directly applicable in resolving safety issues.

Table 3 lists of all current thermal hydraulic projects and shows that the main focus is at Ih'EL with supporting expertise at other laboratories and universities Appendix B shows the program brief for technical integration at INEL for FY 1987. The major tasks to be performed by INEL in its role of primary contractor and assistant to the NRC staff in technical integration are as follows:

A. Provide syntheses of completed research to assist in incorporating research results into the regulatory process in such areas as:

a. Steam generator heat transfer during transients,

b. Steam generator liquid holdup and reactor vessel level depression,

c. Best-estimate large-break loss-of-coolant accident prediction versus evaluation model comparison,

d. ECC bypass in downcomer,

e. Fluid mixing during high pressure injection,

f. Consequences of feedline and steamline breaks,

g. Influence of control system failures on plant transients,

h. Multidimensional flows in core during large-break loss-of-coolant accidents in PWRs (cross flow, chimney effect),

i. Water hammer,

j. Critical heat flux,

k. Blowoown heat transfer, anc

1. First time applications of the code by NRR to new problems, when required.

l 1

l 23

,_ . _.._ _ __ __ . . _ - - _ . . _ . . . _ . - . . ~ -_ .

i l

\

B. Computer codes:

a. Maintain the code,

)

ib. Quantify the code uncertainty with respect to regulatory . issues and  :

4 objectives,

c. Assure consistency of code calculations,

d. Assess the code scaling capability, and 1

i e. Assess the effects of any code shortcomings and identify any compen-

sating errors (i.e. getting the right answer for the wrong reason.

• C. Provide rapid technical response as requested by NRR to urgent regulatory-issues raised as a result of transients in operating power plants, such i as:

4 a. Implications for feed and. bleed in B&W plants, and ,

b. Consequences of instrument tube failures in Westinghouse plants..

D. Provide support for special studies and projects such as:

4 l a. Technical basis for proposed ECCS rule revision.

4 l b. Improve capabilities of NRC Black Fox training simulator, and

c. Techr.ical assistance te NRR on a priority basis, while minirizing impact on research projects.

l' E. Provide options and recommendations to NRC for planning future research l requirements with respect to:

, a. Providing technical basis for NRC audit of industry requests

concerning

improving plant capacity factors; improving technical j specifications; and irproving plant design and safety systems, l i

! b. Evaluating effects of design differences between nonstandardized

{ plar,t designs, and

c. Assisting NRC and industry to implement research to achieve better i operator training, better operator procedures, and better diagnostic l aids.

F. Continuing Experimental Capability. The NRC has had the ability to per-ferra integral systems tests in facilities representative of each vendor geometry. These facilities will all soon be closed. Unless' action is taken, the NRC will lose the ability to obtain tirely.integrcl system data that may be needed in the future to assess analysis methods assist in evaluating LWR response during operational transients, evaluate new and improved reactor designs, and assess operator guidelines. An important mechanism for maintaining expertist would also be lost. A study is, therefore, underway to assess alternative integral facility approaches.

24 i

, . . _ _ - - - _ . _ - - _ - _ , _ . _ . . - . _ , _ . . - _ _ -. . - - - _ . - _ . - - _ . - _ _ _ . -~- - _ ,, -

L. Topical Sur: aries of Research Results The products of research programs have normally consisted of numerous individu-al contractor reports providing results of individual portions of the overall program. These reports are aimed at documenting research results as opposed to presenting information in a fonn that can be readily incorporated into the reg-ulatory process or to addre:is the resolution of the particular issue that orig-inally motivated tbc research. There is a need, therefore, for summary reports that integrate and assess the significance of individual reports and answer the original concerns. Such reports will be prepared and will lead to staff positions on issues.

Thermal hydraulic research has generated a large amount of information. The need to synthesize and implement research results is apparent in view of the resource expenditures being allocated to thermal hydraulics, currently about

$60M per year internationally and $1400M total to date. Most of this information resides in large numbers of programatic reports. The existing research infonnation must be documented in forms that can be readily retained and utilized in the long term or else much of it will be effectively lost. The selection of topical summaries would be made on an issue basis and defined by

+he RRRG. As an example, a topical summary could be prepared on the response of Babcock and Wilcox plants to loss of feedwater events, as indicated by pertinent experimental programs and code calculations.

6. Revision of Policy and Planning Guidance Report (NUREG-0885)

The next version of the Policy and Planning Guidance should include wording that specifically addresses the subject of thermal hydraulic technical i r.tegra t f or.. Ne revision will depend on the final approved integratior plan, however, specific reference to thermal hydraulic intercration could be included Section II, " Assuring the Safe Operation of Licensed Facilities" or in Section VIII.E, "Research."

7. Performance Evaluations The effective implementation of improved technical integration requires added comitments fror appropriate NRC management and staff. An effort must be made to encourage and recognize such participation. To ensure that NRC management and staff members have proper personal incentive anc hnefit from adding tech-nical integraticn functions to their other duties, performance evaluations for appropriate personnel will be revised accordingly. Suggested wording for per-sonnel assigned to the RRRGs is shown in the following. Appropriate woroing will have to be developed for management. For reference, existing performance appraisals for SES and non-SES personnel are shown in Appendix C.

26

4

" Critical Elerent Provide for effective utilization and integration of,research results in the regulatory process to achieve the maximum benefit from NRC research. Represent office in regulatory research review groups (RRRG). . ' Represent office at peri-odic briefings of the EDO, the Comr.ission, or the ACRS on technical integration of activities among NRC staff and with NRC contractors, U.S. industry, and international partners.

f I

Performance Standards

1. Attend meetings of assigned RRRG. Assist in defining regulatory issues to j be resolved and assure that research provides adequate closure.

2. Attend meetings of assigned research management groups for major projects.

Assist in assuring that research is focused on achieving defined regula-tory objectives.

3. Attend periodic briefings of the EDO, the Commission, and ACRS on tech-nical integration. Assist in assuring that technical activities are adequately coordinated and integrated among NRC staff, NRC contractors, U.S. industry, and international partners."

8. Periodic Briefings of EDO, Conr.ission, and ACRS i Following briefings and consultations of the appropriate office directors, periodic briefings of the EDO, the Commission, or the ACRS should be provided by the NRC staff on the implementation of technical integration. This will ensure that tFe subject continues to receive the appropriate attention and that the status of thermal hydraulic issues and their resolution are reviewed periodically. These briefings should be held approximately quarterly or semiannually. An agenda would be distributed prior to the briefings.

I I

l

?E

IV. Schedule and Pudcet Recuirements for Technical Integration NRR and RES are proceeding to define the staff assignments for implementing the agreed upon plan. RES has defined the technical integration contractor inter-face and responsibilities including establishment of specific contacts in each sponsoring and performing office and the contractor organization.

Thermal hydraulic topics for technical integration were identified jointly by the sponsoring, performing and contractor organizations. As technical integration contractor, INEL has prepared a report approved by RES and NRR on the complete functioning, plans, programs, and schedules as appropriate (see Referencelist). INEL will provide at least one technical report on a technical integration issue by August 1, 1986.

The technical integration center budget requirements will be determined by RES and the RRRG.

V. Acknowledgement The criginal draft of this plan was prepared by David Bessette who was responsible for drafting many of the plans and recommendations.

VI. References

1. Memorandum from Harold Denton, to Robert Minogue, dated March 9,1984,

" Proposal for Improved Benefits from NRC Research".

27

-- - - . . -- -- . .. . - - .- - = . . . - - - .

o l

APPENDIX A 1

Craf t Charter of the Regulatory Research Review Group ,

for Thermal Hydraulic Activities  !

i A NRR/RES Regulatory Research Review Group (RRRG) shall be established and

maintained.

Purpose f The purpose of the RRRG is to assure joint accountability in issue identification and resolution by providing recomendations as follows

;

• Identify and prioritize the regulatory objectives or safety issues;

• Consioer budget requirements to meet the determined objectives; I

• Regularly review and report to the Office Directors of RES and NRR as to whether the scope of research and technical assistance projects l

! are appropriately focused and tire schedules are adequate to satisfy I >

i the needs of the regulatory program.

' Consider program curtailments due to budget reductions and provide l

recosmiendations to the Office Director of RES and NRR on reordering l of priorities;

• Establish anc maintain RES-NRR cocrdination at the managenent and working levels as well as coordination with other offices, as l

l appropriate;

• Review the execution of research and technical assistance to assure f

j that specific tests, analyses, and reports are associated with specific regulatory objectives or safety issues; i

Monitor technical progress and schedule of research to assure appropriate and timely progress is being made toward meeting objectives;

• Promote technical integration of thermal-hydraulic research into the regt.latory process by reviewing research results in anticipation of transferring information in forms that are readily usable to NRR;

.-,,-,,--,,--,--,n- ,~~.m,--,,, -=.---ynw,. , . , , , . . , .,.pp,..n,-n- ,n,,e--_..n- , ,., r-,..------n.,--.,--n--- w,-,-----,,,-- ~,----.e . - - - - .

Review the plans ar.d budget for work to be performed by the thermal hydraulic technical integration center; Discuss incorporating results into reguletory process through revising rules and regulatory guides, where appropriate, and through use of l analytical methods and computer codes;

• Review significant code development and code assessment work; and provide recommendations on how resources should be expended on thermal hydraulic codes to meet NRC needs; Participate with ADM and IRM to review the adequacy of agency i guidance on code s.aintenance and documentation. l Assure that research and technical assistance are coordinated to eliminate unnecessary duplication; i

Regulatory review the contractor's research of industry and foreign experience to detennine the applicability to the NRC regulatory program.

Frequency of Meetings The RRRG will nomally meet quarterly but may meet more or less often as required. Ad hoc meetings ray be called in response to urgent issues.

Secretary A Secretary to the RRRG will be provided by RES. Following each meeting, draft minutes will be prepared and circulated te RRRG members. Once agreement has been obtained that the meeting record is satisfactory, the minutes will be distributed to appropriate office management. The minutes will ir.clude issues discussed and recommendations made. The minutes will highlight recommenced decisions or actions requiring office management discussion or approval.

Issues that cannot be agreed upon by the RRRG will be highlightec for appropriate management action.

A-2

RRRG Membership and Chairman The RPRG Chairm6n will be forn: NRR. The group will include members at the Division Director level from NRR, RES and 18E. Membership on the RRRG will be jointly determined by the office directors concerned. If the following members cannot attend a meeting, they shall designate alternates to attend in their place. The proposed membership will be:

Chairman: Deputy Director, Division of Safety Review and Oversight, NRR Director or Deputy Director, Division of Reactor System Safety. RES The following members shall attend meeting on an ad hoc basis according to the relevance of agenda topics of specific meetings to the responsibilities of their divisions:

Director, Deputy Director, or Assistant Director, Division of Boiling Water Reactor Licensing, NRR Director, Deputy Director or Assistant Director, Division of Pressurized Water Reactor Licensing, A, NRR Director, Deputy Director or Assistant Director, Division of Pressurized kater Rcector Licensing, B, hkR Director or Deputy Director, Division of Regulatory Applications, RES Director or Deputy Director, Division of Emergency Preparedness and Engineering Response, I&E Other Attendance Representative (s) from the thermal-hydraulics technical integration center will attenc meetings, as required, in a consultirs capacity. Additional attendance is based on the subject matter of the meeting. Representatives of ILE, AE00, or other NRC staff will be invited wher.ever appropriate, as well as technical consultants, as needed.

e A-3

Responsibilities of NRP and RES i NRR is responsible for assuring that the group using the research is also the group approving its initiation, continuation, and conclusions. It is also i responsible for assuring the continuity of purpose and objectives is maintained, with allowance for new safety issues or priorities based on operating experience.

RES is responsible for identifying existing infonnation available from domestic l and foreign sources, assessing the total research support needed, fonnulating research program and schedule, and contracting for required research. It is responsible for monitoring technical progress and schedule, assuring that the research is technically sound, and that progress is being made toward achieving the stated objectives. This infonnation shall be reviewed with NRR through the RRRG periodically to ensure that it is compatible with NRR objectives. It is also responsible for integrating relevant infonnation from related research.

i RES is responsible for providing for peer review of research results.

! RES and NRR share responsibility for incorporation of the results into the regulatory process including revising rules and regulatory guides, where appropriate. RES and NRR are alst responsible for pericdic review with ACRS of i the regulatory objectives or safety issues, progress toward meeting these i objectives, and incorporation of research results into the regulatory process. 1 i

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Appendix B FY 1986 PROGRAM BRIEF PROGRAM: DAE TITLE: Thernal-Hydraulic Technical FIN: A6328 Integration Center CONTRACTOR: INEL SITE: Idaho Falls STATE: Idaho NRC TECHNICAL MONITOR: L. M. Shotkin and D. Solberg PRINCIPAL INVESTIGATOR: P. North OBJECTIVES: (1) Maintain technical cognizance of all thermal-hydraulic research and related safety issues.

(2) Assist NRC in planning and performing research and report periodically on research accomplishments.

(3) Maintain cooperative efforts with other DOE laboratories, U.S. nuclear industry, universities, and international research organizations.

BUDGET ACTIVITY: 601920 FY 1986 OBLIGATION: $350K FY 1986 SCOPE:

1. Provide a plannina document describing the implementation and scope of the Thermal Hydraulic Technical Integration Center based on the February 1986 draft IE9 and discussions held between NRC, DOE, and EG&G staff during the meeting at INEL on February 10-12, 1986. This dccument should be provided to NPC for coment within two weeks.

2. Initiate a long term study of the applicability of the NRC thermal hydraulic computer codes to calculate various transients in light water reacters. The importance of identified code deficiencies should be evaluated based upon risk considerations, licensing needs, and the need to l address safety issues arising from actual events in operating reactors.

Recorrendations for additional required research should be provided in FY 1986.

The initial study should concentrate on the appicability of both RELAP5 and TRAC to transients in plants of B&W design. The results of existing and ongoing research at LANL, B&W and elsewhere, as well as preliminary l

results from ICAP, should be used as a basis for this study. Additional calculations may alsn be required to confim or extend existing research.

An interim report sumarizing current code applicability to B&W plants should be provided in FY 1986.

3. Review the Technical Basis Document for the pro;:osed ECCS Rule Revision and perform other additional tasks on this document.

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4 Evaluate the possibility of merging the existing TRAC-BWR and TRAC-PWR codes and provide the results of this evaluation to NRC. Include LANL input into this evaluation.

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APPENDIX C CURRENT PERFORMANCE APPRAISAL ELEMENTS WHICH DEAL WITH TECHNICAL INTEGRATION OFFICE OF RESEARCH 0FFICE DIRECTOR (SES)

CRITICAL ELEMENT:

Conduct a research program in an efficient and businesslike manner that meets 4 the needs of NRC's licensing offices in support of specific regulatory deci-sions, and issue on a timely basis needed regulations and regulatory guides.

PERFORMANCE STANDARDS:

Meet the goals of the EDO Program Guidance, as amended during the course of the year, and deal efficiently with unanticipated events. Deal effectively with programatic issues.

DIVISI0f; DIRECTOR (SES)

CRITICAL ELEMENT 1 Conduct an ef fective research program in a businesslike manner that meets the needs of NRC's licensing offices in support of specific regulatory decisions, and issue or a timely basis needed regulations and regulatory guices.

PERFORMANCE STANDARDS (a) Develop operating plan and submit to Director, RES, for approval by August 1, 1985.

I (b) Substantially cor.plete the operating plan, as amended (with concurrence of Director, RES) during the course of the year.

NOTE: The operating plan contains items which are to be eccomplished within the rating period. The performance rating is not only based on the items ac-complished but also (and of more it;crtance) ce the manner in which they are accomplished. The factors taken into account in this regard include cost ef-fectiveness, regulatory usefulness, degree to which results are accepted, and ability to achieve closure, i

I BRANCH CHIEF (SES)

CRITICA'. ELEMENT 1:

Conduct a research program on Therwel Hydraulic Transients in an efficient and businesslike sanner that is responsive to Connission needs, supports NRC's licensing offices, and attempts to achieve closure on safety issues.

PERF0PMANCE STANDARD $:

(a) Develop Branch operating plan and submit to Director, DAE by August '1,1984.

(b) Substantially meet the goals of the Branch operating plan as amended by RES renagement and budget constraints.

NOTE: The operating plan contains items which are to be accomplished within the rating period. The performance rating is not only based on the items ac-complished, but also (and of more importance) on the manner in which they are accomplished. The factors taken into account in this regard include cost ef-fectiveness, regulatory usefulness, degree to which results are accepted, and ability to achieve closure.

PROGRAF MANAGER (N0h-SES); (TYPICAL)

CRITICAL ELEMENT 2C:

Ensures that contractor's work under his guidance is focused to assist NRR and other user offices in resolving licensing issues. Effectively communicates technical results of programs.

PERFC:"ANCE STANDARDS:

Arranges meetings and phone calls with user office personnel to discuss program scope and schedules. Writes RILs on completed projects.

Provides concise summaries of programs for weekly reports. Provides effective input to the Long-Range Research Plan and Annual Report.

Discusses prcgram briefs, program assumptions, and 189's with user offices for commerts.

On cocoerative prog, rams, such as those with EPRI or vendors, provides effective coordination and assures that NRC safety and licensing issues are addressed.

CRITICAL ELEMENT SC:

Ensures that work performed under bilateral thermal hydraulic agreements will assist NRR and other NRC offices in resolving licensing issues. Effectively comruricates technical results of programs.

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PERFORMANCE STANDARDS:

Arranges meetings with representatives of NRR and other NRC offices to review and discuss the results of bilateral therwel hydraulic agreements addressing some licensing, regulatory, or generic issues.

Writes Research Information Letters on specific topics by integrating the re-sults of various reports from different participants in international coopera-tive agreements into consistent readable documents.

Serves as a member of committees and task forces composed of members from dif-ferent NRC groups for the purpose of performing specific study or resolving a generic regulatory issue. Provides the committees and task forces with related inforwetion obtained through international agreements.

Maintains liaison and controls the flow of information between international partners, responsible RES project managers and contractors, and the appropriate NRR and other NRC offices.

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0FFICE OF NRR REACTOR SYSTEMS BRANCH CHIEF (SES) (before recent reorganization)

CRITICAL ELEMENT 3C:

Meets 75 percent of the target dates mutually agreed to with DST for input on review of LRRP, RES budget, and other substantive reviews of rules, regulatory guides, standards, and research activities.

PERFORMANCE STANDARDS:

Provide extensive specific connents on LRRP, in particular relating LRRP to previous user need letters prepared in RSB. Participate actively in review groups. Meet with RES branch chief regularly to go over research needs. Pre-pare user need letters.

REACTOR SYSTEMS BRANCH SECTION LEADER CRITICAL ELEMENT 3C:

Identify, develop, and evaluate research studies and programs to be sponsored or undertaken by RES.

PERFORMANCE STANDARDS:

Demonstrate sound knowledge of nuclear engineering and related engineering fields through ability to effectively work with peers, NRC management, licen-sees, comittee members, suboroinates, and others in arriving at improved tech-niques and procedures.

GS-14 REVIEWER (TYPICAL NONCRITICAL ELEMENT:

Identify and evaluate the need for confirmatory research to be performed by RES. Participate in Research Peview Groups and recorrend research or changes l in research programs.

PERFORMANCE STAhDARDS:

Recomendations for research indicates that the employee is alert to the need for changes in standards and for research and initiates action in a timely manner.

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