ML25196A405

05-28-76 Activities of the Advisory Committee on Reactor Safeguards (ACRS)

ML25196A405
Person / Time
Issue date:	05/28/1976
From:	Moeller D Advisory Committee on Reactor Safeguards
To:	Rowden M NRC/Chairman
References
Download: ML25196A405 (1)

Text

ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUCLEAR REGULATORY COMMISSION Honorable Marcus A. Roviien Chairman WASHINGTON, D. C. 20555 May 28, 1976 U. s. Nuclear Regulatory Commission Washington, OC 20555

Subject:

ACTIVITIES OF THE ADVISORY COMMITI'EE ON REACTOR SAFEGUP...RDS (ACRS)

Dear Mr. Rowden:

On January 13, 1976, the Co:mmittee forwarded a letter (Attachment 1) to Chairman Anders, providing background information on ACRS activities and responsibilities. Subsequent to this letter, the Committee was asked to provide additional information.

'As previously indicated, the ACRS reviews applications for construction permits and operating licenses for power reactors, fuel reprocessing plants, and certain test and research reactors. It also reviews appli-cations for standardized plants including applications for the nuclear island (e.g., GESSAR-238), the nuclear stea'1l supply system (e.g., P-ESAR-41),

and the balance-of-plant (e.g., ffi*JESSAR).

In addition, it has been the practice of the Committee to review the proposed corrective 1neasures when, because of operational experience or new safety requirements, a facility requires substantial ch&,ges in design, changes in operational procedures, or repairs (e.g., Bro~ms Ferry Nuclear Power Station). The Committee also conducts reviews, as requested by the Corrnnission, of non-licensed ERDA and DOD reactors, such as t.lie Savannah River and Hanford Reactors, naval reactor plants, the Fast Flux Test Facility, the CRBR and the Advanced Test Reactor and Engineering Test Reactor at the Idaho National Engineering Laboratory.

In addition to the above, the Committee reviews a large number of ge-neric items related to nuclear plant safety standards and guides and to NRC Regulations. The Committee also provides advice on safety research programs, and from time to time the ACRS has established ad hoc Work-ing Groups to review and make recommendations regarding specific safety issues. Much of the latter effort has been in response to specific re-quests from the Commission.

2760

Honorable Marcus May 28, 1976 I. Review Items - Land Based Light Water Power Reactors The Committee's review of proposed facilities includes consider-ation of the General Design Criteria (Appendix A) of 10 CFR Part 50 as well as the requirements of other safety related Appendices to Part 50 (e.g., Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants; Appendix E, Emergency Plans for Production and Utilization Facilities; Appendix G, Fracture Toughness Requirements; Appendix H, Reactor Vessel Material Surveillance Program Requirements, etc.).

These activities include investigation of matters such as the suitability of the proposed site, the effect the reactor may have on the surrounding population, the effect of site-related parameters on the reactor plant itself (e.g., floods, seismicity),

the design of the facility including plant security and safeguards for special nuclear material, the competence of the construction and operating organization, the training and qualification of operating person.~el, the quality assurance program,the operating and emergency plans, the periodic test and inspection programs for the facility and the results of operating experience at the plant.

In the Committee's review, consideration is given to the develop-ment and confirmation of analytical models used in the design and analysis of plant performance, including systems analysis, relia-bility analysis and accident analysis. Attention is also given to the safety margins provided and the redundancy and diversity in-corporated in the plant design.

The Committee has limited its interest in envirornnental matters to those questions related to public safety in areas within the COmnittee's purview. Although additional aspects of this subject must be considered by the NRC in accordance with the National Environmental Policy Act, it has been ACRS practice not to become involved in these issues.

The types of expert~se needed in the Committee membership can be discerned from the above description. '!he Comnittee needs members with substantive knowledge and experience inJnuclear power plant design, construction and operation; siting practices; material properties; nuclear fuel design, manufacturing and use; fuel 2761

Honorable ~1arcus May 28, 1976 reprocessing; radioactive materials handling and transport; emergency planning; reliability and risk assessment; nuclear waste management and health physics; nuclear technology; research and developnent; nuclear industrial security and safe-guards; and industrial management of nuclear facilities., '!he paragraphs which follow provide additional details concerning the types of matters reviewed by the Committee:

1. Site and Environment A.

Population distribution and how it might influence evac-uation and individual and total doses to the population, in the event of an accident. 'Ihe presence of other activities which might have an impact on reactor safety is considered, e.g., the nearby location of industries involving toxic or explosive material, the presence of airports or missile sites, and transportation routes over which hazardous materials may pass.

B. Meteorology and its effect on routi.l'le and accidental releases of radioactive materials to the atmosphere, and the possible effects of severe atmospheric dis-turbances such as high winds, tornadoes, and hurricanes on reactor structures.

C.

Seismology, geology and foundation material as they re-late to seismic design of the proposed facility including the probability of earthquakes of various magnitudes and intensities which might affect the site through surface faulting, subsidence, dilatancy, and liquefaction.

D.

Hydrology in regard to potential flooding in the vicinity of the site, the presence of aquifers which might become contaminated in the event of a serious accident, and the adequacy of the cooling water supply during periods of drought or low water flow.

E. Tsunamis, seiches, and other types of wave actions and their effects on plant structures for reactors located near large oodies of water.

2762

Honorable Marcus A. Ro\\'rlen May 28, 1976 F. Environmental monitoring progra."'IIS to establish radiation background levels and to determine the amount and distri-bution of radioactive materials as a consequence of routine or accidental releases.

2.

Reactor A.

The mechanical design including the core (e.g., fuel rods, fuel assemblies, and control elements), reactor internals (e.g., core support plate, core shroud, and thermal shield),

and control rod drive asse.'ilblies.

Included in this review is a consideration of material characteristics such as strength, creep, corrosion resistance, and radiation damage.

Also included are possible flow induced vibrations, blowdown forces during a postulated loss-of-coolant accident, seismic response, quality control, testing, and the reliability of components.

B.

Nuclear design as it pertains to items such as core reac-tivity and control requirements, reactivity coefficients, power distribution, spatial stability, and analytical tech-niques (including comparison of calculations with experi-ments).

C.

Thermal and hydraulic design including considerations of items such as core hydraulics, heat transfer correlations, fuel temperatures, and the ability of the fuel to withstand expected transients throughout its life.

3. Reactor Coolant System A.

A review of the layout and design of the components of the reactor coolant system including the reactor pressure vessel, the steam generator, reactor coola.~t pumps, the*pressurizer, the reactor coolant piping, support structures, and seismic restraints.

B.

The design bases for the reactor coolant system inclu:ling a review of the loading combinations used and the codes which have been applied (e.g., sections of the ASME Boiler and 2763

Honorable Marcus May 28, 1976 Pressure Vessel Code). These include the design bases for steady state and transient conditions, as well as the seismic design bases, materials used in the coolant system and their properties (such as the nil ductility transition temperature and the susceptibility to stress-corrosion cracking). Also included are considerations of controls on the che.~istry of the water in the reactor coolant system and the secondary syste.~.

c. Tests and inspections of the primary system COmfX>nents.

These include the initial nondestructive testing of pri-mary systen components, the inservice inspection program, and the evaluation of the significance of any fla~,s or de-fects observed.

D.

Detection, location and evaluation of leakage from the pri-mary syste.rn.

Included are the methods and sensitivity of locating and evaluating the leakage.

4. Containment Design A.

The basis and adequacy of the design for. various loads on the contain.11ent including those which might result from earthquakes, tornadoes, operating thermal stresses, and various accident conditions.

B.

The adequacy of the containment materials including in-spection, testing, and surveillance programs for the materials.

C.

Protection of the plant from missiles generated inside and outside containment, such as those resulting from turbine, pump or pipe failures, and the ability of the containment to withstand missile and aircraft impact, as appropriate.

n. Structural analysis methods used to evaluate matters sue..~

as stresses near large openings, possible failure of ten-dons, thermal and hydraulic loads resulting from actuation of various systerns, and seismic loads.

E.

Provisions for periodic testing and inspection of containment.

F. Evaluation of the adequacy of various containment design concepts such as pressure suppression containment systems, subatmospheric containment systems, and ice condenser con-tainment systems.

2764

Honorable Marcus May 28, 1976 G.

Corrosion protection including consideration of items such as grouting vs greasing of prestressing tendons, and the use of cathodic protection.

5. Engineered Safeguards Review of the adequacy of the design bases, codes, tests, and quality assurance for various engineered safeguards systems.

These include i terns such as e,iergency shutdo\\"m syste."'DS, safety injection systems, core spray systems, containment spray sys-tems, and containment building filtration systems.

6. Instrumentation and Control Systems A.

The design bases, system layout, logic syste."tl operation, and the initial and periodic testing of the reactor control and protection syster.t instrumentation. Also considered are the adequacy of redundancy, separation, diversity and re-liability.

B.

These items are also reviewed for the engineered safeguards instrumentation, in-core monitoring systerr.s, and the radia-tion protection instrumentation.

7. Electrical Systems Electrical power systems are reviewed, particularly in regard to reliability of both off-site power and on-site emergency pC>\\oler systems, to provide the necessary electrical power to maintain the reactor in a safe condition under various normal and abnormal conditions including assumed failures of part of the electrical power system.

8. Auxiliary Systems Matters such as the design bases, applicable codes and stan-dards, reliability, quality control, and testing and inspec-tion of various auxiliary systems which affect nuclear safety are considered. These include items such as the chemical and volume control syste-n, the shutdown cooling system, various other cooling systems, the fuel handling system, ventilation systems, and fire protection systems.

2765

Honorable Marcus May 28, 1976

9. Steam and Power Conversion Systems Consideration is given to the following items as they relate to reactor safety - the turbine-generator and main trans-formers, main steam dump system, main turbine condensers, condensate and feedwater systems, and auxiliary feedwater systems.

10. Radioactive Waste Systems and Radiation Protection The design bases for the liquid, gaseous, and solid waste management systems are considered along with matters such as methods of operation, tests and inspections, and operating experience. Radiation protection shielding, area radiation monitoring systems, and general radiological health and safety features as they affect both members of the public and the plant operators are reviewed.

11. Reactor Construction and Operating Organization Also reviewed are the plant construction and operating organiza-tions, including the quality assurance organization, the plant safety review organization, and the reactor operating organiza-tion, and the training and qualification of operating personnel.

12. Accident Evaluation The Conunittee reviews a wide variety of possible accidents in-cluding occurrences such as a control rod withdrawal accident, a loss-of-coolant accident, and fuel handling accidents, and their consequences. This review involves many aspects of science and engineering, e.g., electrical engineering as it pertains to reac-tor controls and the operation of engineered safeguards, nuclear physics as it relates to items such as reactivity addition rates and the rate of power generation in the reactor core, chemical engineering as it relates to the release and interaction of radioactive nuclides with other materials, mechanical engineering as it concerns the capability of mechanical components to with-stand various forces, civil engineering with respect to the stability and integrity of structures such as the containment, meteorology relative to dispersal of fission products in the atmosphere, and public health in terms of the potential effects on plant personnel and nearby population groups from the inad-vertent release of radioactive materials.

2766

Honorable Harcus A. P,O'wden May 28, 1976 II. Review Items - Other Plant Types In addition to the evaluation of land based light water p0\\>7er reactors, the Comnittee reviews a variety of items related to other types of reactors. Listed below are several examples of the additional considerations involved in these reviews.

1. Floating Nuclear Plant A.

Matters of the seaworthiness of floating platforms, the adequacy of anchorage systeros, the effects of collisions with the facility by various types of ships {including those containing LNG).

B.

The stability of breakwaters designed to protect floating plants including considerations of wave action, subsidence and liquefaction.

C.

The effects of the release of radioactive materials to an ocean environment.

2.

Liquid t1etal Fast Breeder Feactors A.

The effects on materials of the use of sodium as the pri-mary system coolant. The effects of the high temperature environment on material properties and performance are also considered.

B.

An evaluation of the amount of energy which might be re-leased due to various accidents and what energy release should be used as a basis for design.

C.

An evaluation of the need for special safety provisions for this type of reactor, e.g., whether installation of a core catcher should be required a.."ld whether a second shutdown system is needed.

3. Eigh Te.-rnperature Gas Cooled-Reactors A.

Special considerations involved due to the presence of a high temperature gas. These include matters such as corrosion, mass-transfer, and the strength and fatigue life of materials.

2767

Honorable Marcus May 28, 1976 B.

The adequacy of the containment including special con-siderations such as its need to function for prolonged periods of time at elevated pressure.

C.

The use of prestressed concrete pressure vessels.

4. Test and Research Reactors The review of Test and Research Reactors can involve a mrnber of additional questions such as those pertaining to ~~e p:>ten-tial safety impact of the tests and experiments to be conducted.

A specific exarnple is the series of tests pro:P()sed for LOFT.

Se Naval Reactors & Production Reactors These reactors involve additional considerations such as national defense.

In the case of nuclear powered vessels, consideration must also be given to their use of service and maintenance facilities in a wide range of locations.

III~ Chemical Processing Facilities In addition to nuclear reactors, the Co:mmittee also reviews the safety of nuclear fuel reprocessing plants. Although many of the same topics are reviewed as for nuclear power plants, there is much greater emphasis on che.~ical engineering and on factors such as safety considerations related to inadvertent criticality.

'IV.

Reactor Safety Research The Corrnnittee also considers the various aspects of reactor safety research including the types of studies needed and progress being made in this field. It does this for both light water power re-actors and for new and advanced reactor types such as the liquid metal fast breeder reactor and advanced gas cooled reactors.

v. Other Subjects The Corrmittee reviews a number of other subjects on its own volition or at the request of the Commission.

These include:

1. Nuclear safeguards and GESMO proceedings which concern matters such as the possible diversion of special nuclear material during the fuel cycle and possible radiation hazards due to the widespread use of plutonium.

2768

Honorable Marcus May 28, 1976

2.

Nuclear reactor inspection which involves matters such as quality assurance and compliance with NRC P-egulations and Technical Specifications.

3.

Reviews of NRC Division 1 Regulatory Guides which include a wide range of considerations of reactor safety.

As previously indicated in the January 13, 1976 letter, members of the Committee have backgrounds in technological areas germane to nuclear safety and have, in their careers, performed duties requiring a maturity of judgment appropriate to assessing risks to the health and safety of the public. An up:lated listing of the specialities of the current ACRS members is given below:

1. Che-rtical plant design, construction, operation and corporate management.

2.

Che..-rtical and nuclear systems thermal/hydraulic perforrrr ance and nuclear fuel performance.

3. Research and developnent ma.~agement, fuel cycle technology, and nuclear materials safeguards.

4. Structural safety, structural research, structural design codes and concrete materials.

5. Electrical and nuclear systems engineering and nuclear reactor operations

6. Radioactive effluent control, radiation protection, and public health.

7. Nuclear reactor thermal/hydraulic performance and safety.

8. Engineering management and nuclear plant equipnent design and construction.

9. Applied physics and fluid mechanics.

10. Thermal and fast reactor physics and safety, systems analysis, risk assessment, and nuclear fuel ele.i-rtent behavior.

2769

Honorable Marcus May 28 1 1976

11. Nuclear materials technology including nuclear fuels, radiation damage effects on materials, non-destructive testing, design, construction and operating codes for nuclear system boundaries, corrosion, and system reliability.

12. Mathematical modeling, fast reactor design and safety, neutron transport theory, and theoretical physics.

13. Nuclear engineering systems analysis, particularly in regard to electrical systems, reactor safety systems, shielding design, and nuclear plant design and layout.

14. Nuclear reactor design, construction and startup, pres-sure vessel design for L\\'1Rs, and nuclear engineering.

Since it may also be of some assistance to the Commission, the areas of specialities of the ACRS Consultants whose appointments are presently scheduled for renewal are listed in Attachment 2. ~is list provides an additional indication of the subject areas where the Committee has believed assistance was necessary and shows to some degree the dis-ciplines needed in ACRS reviews.

In the selection of new ACRS ~lernbers, it may be useful to note specific areas in the regulatory process which lie outside the purview of the ACRS.

These include the following:

1. Environmental effects (other than those affecting the health and safety of the public).

2.

Common defense and security (in licensing cases for commercial plants).

3. Preservation of historical landmarks.

4. Antitrust matters.

5. Cost-benefit analyses.

6. Aesthetic considerations.

7. Financial qualifications.

2770

Honorable Marcus May 28, 1976

!;*le hope this additional information will be helpful to the commission.

Should additional questions remain or if we can be of further assistance, do not hesitate to let us know.

Attachments:

1)

Dade W. Moeller Letter to William A. Anders, dtd 1/13/76

2)

List of ACRS Consultants 2771 Sincerely yours,

~{),~~

Dade W. Moeller Chairman

ATTACHMENT l ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUCLEAR RE.GULATORV COMMISSION WASHINGTON, D. C. 20555 January 13, 1976 Honorable William A. Anders Chairman U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Subject:

ACTIVITIES OF mE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)

Dear Mr. Anders:

In response to your request for information that would assist the Commission in selecting new ACRS Members, we are ple"lsed to prc:,ride the following information regarding activities carried out by the Committee. contains copies of Section 29 and 182(b) of the Atomic Energy Act of 1954, as amended, which set forth the legislative basis for the Committee's functions.

The ACRS reviews applications for construction permits and operating licenses for power reactors, fuel reprocessing plants, and certain test and research reactors. It also reviews applications for standard plants including applications to manufacture reactor facilities (e.g., the Floating Nuclear Plant), applications to construct and operate nuclear power reactors of essentially the same design to be located at different sites (e.g., Standardized Nuclear Unit Power Plant System), and standard designs for nuclear power plants (e.g., General Electric Standard Safety Analysis Report and Stone & Webster Engineering Corporation Standard Safety Analysis Report) submitted for NRC Staff and ACRS review.

When, because of operational experience or new safety requirem~nts, a facility requires substantial changes in design, changes in operational procedures, or repairs (e.g., Browns Ferry Nuclear Power Station), the ACRS reviews the proposed corrective measures and provides advice to the Commission as to whether the proposed measures insure adequate prot~ction for the health and safety of the public.

The Committee conducts reviews, as requested by the Commission, of non-licensed ERDA and DOD reactors, such as the Savannah River and Hanford Reactors, naval reactor plants, the Fast Flux Test Facility, and the Advanced Test Reactor and Engineering Test Reactor at the Idaho National Engineering Laboratory.

2772

Honorable William January 13, 1976 The Committee's reviews in all of these areas involve technical evaluations of those factors which affect the health and safety of the public.

These factors include items such as: site characteristics, plant design, quality assurance, and operating, emergency, test, and inspection procedures.

Specific topics within these ca.:.egories include:

seisDicity, geology and meteorology, population distribution, plant design features and related analytical model assumptions and techniques, fuel element design, core peaking factors, primary system boundary design, design of engineered safety features such as ECCS, and d*~:sign of control and safety systems.

The results of plant operations are of interest to the Committee in considering the effectiveness of plant design features and the operating organization.

In addition to its reviews of specific projects, as outlined abov~, the Committee also reviews a large number of generic items. is a list of typical generic matters on which the Commit tr.ca has issued reports, and Attachment 3 is a partial list of subcommittees established for con-tinuing review of generic matters.

An important activity in this latter category is the review of NRC Division 1 Regulatory Guides.

The Committee also ~rovides advice on safety research programs.

The Committee has established from time to time ad hoc Working Groups to review and make recommendations regarding current matters, frequently in response to specific requests from the Commission.

A list of these Wor.king Groups is included as Attachment 4.

Members of the Committee have a background in one or more technological areas germane to nuclear safety and have performed duties requiring a maturity of judgment appropriate to assessing risk to the health and safety of the public.

The specialities of the twelve present members are listed below:

1.

Chemical plant design, construction, operation and corporate management.

2.

Chemical and nuclear systems thermal/hydraulic performance and nuclear fuel performance.

3.

Research and development management, fuel cycle technology, and nuclear materials safeguards.

4. Structural safety, structural research, structural design codes and concrete materials.

2773

Honorable William 5. Electrical and nuclear systems engineering and nuclear reactor operations.

January 13, 1976

6.

Radioactive effluent control, radiation protection, and public health.

7.

Nuclear reactor thermal/hydraulic performance and safety.

8. Nuclear power reactor operations and radioactive waste management.

9.

Engineering management and nuclear plant equipment design and construction.

10.

Applied physics and fluid mechanics.

11.

Thermal and fast reactor physics and safety, systems analysis, risk assessment, and nuclear fuel element behavior.

12.

Nuclear materials technology including nuclear fuels, radiation dam~ge effects on materials, non-destructive testing, design and construction codes for nuclear system boundaries, corrosion, and system reliabil:1.ty.

It has been the experience of the Committee that its members should possess the following qualifications:

a)

Competence in an area of science or engineering related to the matters coming before the Committee.

b)

Mature judgment in their fields of specialization and the ability to extend that judgment to the evaluation of other scientific or technological matters outside those fields.

c) Administrative and management experience and ability as required to fulfill the duties of a subcommittee chairman responsible for the development of information and the preliminary review of nuclear plants and generic problems or studies.

The Counnittee has attempted to have a membership representing a varied group of applicable disciplines, but it is not possible to have every discipline represented.

This has not proved to be a problem because of the use of consultants in support of the Committee.

2774

Honorable William January 13, 1976 There are a number of areas regarding nuclear facilities that the Committee does not consider specifically in its review.

Although the Committee is concerned with the radiolo_gical consequences to man of possible accidents and routine radiological releases, i> does not perform environmental reviews, per se, for reactor projects or fuel reprocessing plants.

The Committee does not review such items as financial qualifi-cations of an applicant or antitrust considerations.

Attachments:

1. Excerpt from the Atomic Energy Act of 1954, as amended

2. Titles of ACRS Generic Reports

3.

ACRS Subcommittees Dealing with Generic Items

4.

ACRS Ad Hoc Working Groups 2775 Sincerely yburs, l>ade W. Moeller Chairman

Excerpt from the Atomic Energy Act of 1954, as amended (Atomic Energy Legislation through 93d Congress, 2nd Session)

--~.:c. 2!l. A1n-1i-..-,nr CmunTIEE ox Ih:.\\cTon 8-\\FF.-

c.r,,1:ns.-Thcrc is herebv t'Stnblished an.AdYisorv Com-1nitr<'e on Hl*actor Safeguards consistin~ of a maximum of fifteen members appointed bv the Commission for tl'nns of four vears each. The Committee shall revie,\\"

!'a fc*ty studies and facility license applicatioD;S referred to it :rnll shall make reports thereon, shall advise the Com-111i,;;;;ion with reirard to the hazards of proposed or exist-i 11~ reactor facilities and the adequacy of proposed re-actor safety standards, and shall perform such other clntic*s as the Commission ma~ request: One m~mber shall he> designated bv the Committee as its Chairman. The mc*rnbers of the Committee shall receive a per diem com-JINbntion for each day spent in meetings or conferences.

or other work of the Committee, ancl all members shall 1w*ein~ their necessary traveling C?r other expen~e~ while N1;,r:1~ecl in the work of the Comnnttee. The provisions of 8ection 163 shall be applicable to the Committec.:-1b Commltt~e or Reactor S:ifei;u:iri!,.

42 u.s.c.

sec. 2039.

W* J*ul,Uc Law 6a-2iiG (i1 Stat. 576) (19;sj), sec. 5, udded sec. 29.

.ACRS Rr1*ort.

Sec. 182 "h. The Ach-isory Committee on R<'nctor Safoguards shall r<',*it'w l'nch application nnclPr scction 10!1 01* se>ction JOI h. for a const.ructiun permit or nu opernting license for n. facility, any application unclcr section 104 c. for a construction permit or an opernting license for a testing facility, any application under sedion 104 a. or c. spe-cifically referred to it by the Commission, :md any appli-cation for an amendment to a construction permit or an nmendment to an opcrnting license under St!ct.ion to:J or 104 a., b.* or c. sp<'cific*nlly r<'f <'rrNl to it. hv t hr. Com-mission, and slm11 sub:rr.it a report thereon,,*hich shall be made part of tho recorcl of the application and aYail-

~hfo _to the public c~cept to the extent that security clnssi-hcahon pnwents d1sclosnrc.6

• 1*11hlk l,:1w i;;,-:.:.,o (71 Stat. 5T0) (Hr:;T), llt'C. 6, llflflerl Bllbsee. b nnd rtilt>UPred forml'r suhsl'cs. h. and c. ns 1
  >1tts. c. 11Dr section 104 a. or c. specifically rt>ferred to Jt by the Comm!s*

  slon. IID<l 1<hnll Knhmlt a rr1,ort tberc*on. which 1111,,11 be m:1df' part of the record or the 11p1>llcatlon 11111I 11vall:1hle to the l'ul,llc, except to the estent that securlty classlfleatwn 11reve11ts dlsclusure.'

  2776

  TITLES OF ACRS GENERIC REPORTS Report on Water Reactor Safety Research Report on Turbine ~.issiles High Temperature, Gas-Cooled Reactor Safety Research Safety Research for Sodium-Cooled Fast Reactors Problems Arising from Primary System Rupture Report on Seismic Research Report on Proposed Reactivity Accident Test Program Proposed Study of the Reactor Hazard and Criteria Problem Report on Review of Siting Policies for Licensing Nuclear Facilities Safety of Operating Reactors Reactor Safety Study - WASH 1400 Status of Generic Items Relating to Light-Water Re~ctors Report on Industrial Sabotage Proposed Regulation on Transport of Radioactive Material Crack Propagation Rate in Sensitized Stainless Steel Alternatives to Staff Position Regarding Anticipated Transients Without Scram (ATWS)

  Intermediate Vessel Tests of the HSST Program Report on EXXON Nuclear Company ECCS Evaluation Model for Reload Cores in PWR' s Systems Analysis of rngineered Safety Systems Control Rods 2777

  ACRS SUBCOMMITTEES DEALING WITH GENERIC ITEMS Accident Evaluation Architect-Engineer Balance of Plant Chemical Processing Plants Codes, Standards, & Criteria Containment:

  Concrete Contain~ent: Steel Electrical Systems, Control and Instrumentation Emergency Core Cooling Systems Environmental Matters Generic Items, Resolution of Inspection & Enforcement Activities Nuclear Merchant Ships Reactor Fuel Reactor Pressure Vessels:

  Concrete Reactor Pressure Vessels: Steel Reactor Safety Research Regulatory Guides Reliability & Accident Probabilities Safeguards for Special Nuclear Material Seismic Activity Siting Evaluation Wa-ste Management 2778

  ACRS AD HOC WORKING GROUPS Anticipated Transients Without Scram (ATWS)

  Double Ended Pipe Break Fire Protection Hydr~geh Generation & Control Hypothetical Core Disruptive Accident for Fast Reactors Makeup of Independent Review & Audit Groups Neutron Noise Analysis Peaking Factors Plutonium Shipping Packages Reactor Safety Study (WASH-1400)

  Safety of Operating Reactors Security of Nuclear Facilities Spent Fuel Storage Capacity Standardization of Nuclear Plants Systems Analysis of Engineered Safety Features 2779

  NAME Allemann, Dr. Rudolph T.

  Ames, Dr. Lloyd Bailey, Mr. Eugene c.

  Bair, Dr. William J.

  Bell, Dr. George I.

  Bement, Prof. Arden L.

  Benedict, Dr. Manson Bennett, Mr. Carl A.

  Bryan, Mr. Robert H.

  Carbiener, Mr. Wayne A.

  Castleman, Prof. A. w., Jr.

  Catton, Dr. Ivan Corten, Prof. Herbert T.

  Crowley, Mr. William Croach, Mr. Jesse W.

  Daniels, Dr. Raymond D'Appolonia, Dr. Elio Ditto, Mr. Steve Dukler, Dr. Abraham E.

  Durant, Mr. Williams.

  Epler, Mr. Elbert P.

  Fauske, Dr. Hans K.

  Foley, Mr. John Fontana, Mr. Mario H.

  Foster, Dr. Richard F.

  Fuquay, Mr. James J.

  Gall, Mr. W.R.

  Garlid, Dr. Kermit Gifford, Dr. F. A., Jr.

  Goldin, Dr. Abrahams.

  ATTACHMENT 2 ACRS CONSULTANTS SPECIALITY Blowdown Heat Transfer and Fluid Swell, ECCS Analysis Inorganic Ion Exchange, Soil-Radioactive Waste Interaction Mechanical Engineering, Waste Management Biological Effects of Pu Fast Reactor Physics Radiation Effects on Core Nuclear Engineering Reliability Engineering Reactor Siting LOCA. Blowdmht Heat Transfer Fission Product Release & Transport Heat Transfer, Natural Convection Relative to Core Meltdown Situations, and Fluid Dynamics Fracture Mechanics, Reactor Vessel Design &

  Operating Conditions Shipment of Radioactive Materials Reactor Engineering Soils Scientist Soils, Foundations & Structures Instrumentation Heat Transfer, Fluid Flow, ECCS Analysis Reactor Engineering Instrumentation & Controls, ATWS Core Thermal-Hydraulics Safeguards Fuel Failure Propagation Aquatic Biologist Meteorogy Strength of Materials for Reactor Components Two-phase Flow and Computer Model Development, ECCS Design and Reliability Meteorology, Atmospheric Diffusion Radioactive Waste Management, Radiological Health and Related Areas 2780

  ATTACHMENT 2 (CONT'D)

  ACRS CONSULTANTS NAME Hall, Dr. David Bo Healy, Dr. John Wo Koffman, Mr. Eugen LaQue, Mr. Francis L.

  Leendertse, Dr. Jan J.

  Lipinski, Dr. Walter c.

  Loeding, Mr. John W.

  Loss, Mr. Frank Lottes, Dr. Paul A.

  MacCready, Dr. Paul B., Jr.

  Mandel, Prof. Philip Mathieu, Capt. Charles E.

  Maxwell, Dr. John c.

  Mercer, Mr. Basil Mirshak, Mr. Samuel Morgan, Dr. Karl z.

  Nicholson, Mr. Richard B.

  Nicholson, Dr. Wesley O'Kelly, Dr. Arlie A.

  Oldendorf, Mr. Lawrence E.

  Oliver, Dr. Jack E.

  Orth, Dr. Don A.

  Page, Dl\\ci Benjamin M.

  Palladino, Dean Nunzio J.

  Parker, Dr. Frank L.

  Parker, Dr. Herbert M.

  Parsly, Mr. Lewis F., Jr.

  Pense, Prof. Alan W.

  Pickel, Dr. T. W.

  Philbrick, Dr. Shailer S.

  SPECIALITY Nuclear Physics Radiological Health, Radwaste Handling Mechanical Engineering Metallurgy & Corrosion of High Nickel Alloys Breakwater Design and Behavior, Dynamics of Fluid Flow, Simulation of Fluid Flow Effects Instrumentation & Control Systems, Design Reliability Chemical Processing Plant Design and Operation Fracture Mechanics Core Thermal Hydraulics Meteorology - Windspeeds for Reactor Design and Dispersion/Diffusion Effects Barge Design and Sea Worthiness Barge, Mooring System & Breakwater for Barge-Mounted Nuclear Power Plants Geology Ion Exchange Systems,Radioactive Waste Manage~

  Reactor Engineering Health Physics Fast Breeder Reactors (Nuclear Excursion)

  Reliability Engineer and Statistician Chemical Engineering Fire Protection Geology and Seismology Chemical Processing Plant Design & Operation Geology Nuclear Engineering Radioactive Waste Management Health Physics Spray System Technology Metallurgy (High Alloy Steels), Fracture Mechanics, Reactor Pressure Vessel Reliability Strength of Materials for Reactor Components-,

  Structural Design Analysis Geology 2781

  ATTACHMENT 2 (CONT'D)

  ACRS CONSULTANTS NAME Plaine, Mr. Herzel H. E.

  Raichlen, Dr. Fredrick Reethof, Dr. Gerhard Richart, Dr. Frank E.

  Richmond, Dr. Chester Row, Mr. Thomas H.

  Russell, Mr. John H.

  Saunders, Dr. Sam C.

  Seale, Dr. Robert L.

  Seed, Dr. H. Bolton Shappert, Mr. Lawrence Shewmon, Dr. Paul G.

  Shumway, Mr. Rex W.

  Siegel, Dr. Sidney Snyder, Mr. Arthur I.

  Solbrig, Dr. Charles W.

  Sozen, Dr. Mete A.

  Squires, Mr. Lombard Stannard, Dr. John Newell Steinbrugge, Mr. Karl V.

  Steindler, Mr. Martin J.

  Stevenson, Dr. M. G.

  Stratton, Dr. William R.

  Swanson, Mr. A. Einer Tetelman, Dr. Alan s.

  Theofanous, Prof.

  Theofanis G.

  SPECIALITY Legal Water Waves & Effects Reliability Engineering, Accident Probability Soils Engineer Pu Biological Effects & Transport Spray System Technology Fast Reactors, Nuclear Transient Effects Mathematical Statistics, Systems Reliability, Fault-Tree Analysis Nuclear Engineering Geology, Seismology, Soil Liquefaction (Soils Engineer)

  Shipment of Radioactive Materials Physical Metallurgy, Surface & Volume Diffusion, Thermodynamics of Surfaces, Kinetics of Reactions in Solids ECCS, Code Development Fast Reactors, High Temperature Material and and Sodium Reactors Pipe Failures ECCS, Code Development Concrete Structures Reactor Engineering Biological Effects of Plutonium Enginee~ing Design of Structures to Withstand Seismic Loadings Chemical Processing Plant Design & Operation Computer Codes Regarding Core Disruption Fast Reactor Design, HCDA's for Fast Reactors, Reactor Safety Calculations Reactor Operations Fracture Characteristics of Steel & Other Materials, Reactor Pressure Vessel Design Fluid Flow & Heat Transfer, ECCS Analysis, Pressure Suppression, Containment, System~

  Analysis 2782

  ATTACHMENT 2 (CONT'D)

  NAME Thompson, Dr. George A.

  Trifunac, Dr. Mihaila D.

  Vesely, Dr. William White, Dr. Merit P.

  Wilson, Dr. Basil W.

  Wilson, Dr. Richard Wilson, Dr. James T.

  Woodcock, Mr. Sidney H.

  Ybarrondo, Dr. Lawrence Zaloudek, Dr. Frank Zittel, Mr. H. E.

  Zudans, Dr. Zenons ACRS CONSULTANTS

  • SPECIALITY Geophysics, Geology, and Seismology Seismology Statistical Evaluation of Pressure Vessel Reliability and Accident Probability Performance of Materials & Structures Under Seismic Loadings Oceanographic Engineering Reactor Siting Seismology, Geophysics Plant Security LOCA, ECCS, Code Development Heat Transfer, ECCS Analysis, Pressure Suppression Containment, Systems Analysis Reactor Safeguards Spray Systems Mechanical Design, Prestressed Concrete Pressure Vessels 2783