ML20035E041

Summary of 385th ACRS Meeting on 920506-09 in Bethesda,Md Re Policy Issues for Certification of Evolutionary & Passive Nuclear Power Plant Designs & Containment Performance Criteria to Accommodate Severe Accidents

ML20035E041
Person / Time
Issue date:	04/09/1993
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-2820, NUDOCS 9304140207
Download: ML20035E041 (45)

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TABLE OF CONTENTS MINUTES OF THE 385TH ACRS MEETING MAY 6-9, 1992 I.

Chairman's Report.....................................

1 II.

Policy Issues for Certification of Evolutionary and Passive Nuclear Power Plant Designs...................

1 III.

Subcommittee Reports 2

Report on the Joint Meeting of the IPE and Severe e

Accidents Subcommittees Held on April 21, 1992......

2 i

Report on the Subcommittee Meeting Regarding the e

GE ABWR Control Room Design, Held on May 5, 1992...

3 Report on the Joint Meeting of ACRS Subcommittees e

on Computers in Nuclear Power Plants Operations and on Human Factors, Held on May 5, 1992...........

3 Report on Subcommittee Meeting on Computers in e

Nuclear Power Plants concerning International Computer Related Activities, Held on May 5, 1992....

4 Trip Report by ACRS Member J.

Carroll on his e

Trip to Japan.......................................

5 IV.

Containment Performance Criteria to Accommodate Severe Accidents..

5 V.

Review of Test Program in Support of the GE Simplified Boiling Water Reactor Design Certification............

7 VI.

Generic Issue B-56, Diesel Generator Reliability......

8 VII.

Implementation of NRC Safety Goal Policy..............

10 VIII. Definition of a "Large Re1 ease';.......................

10 IX.

NRC Standard Review Plan Update and Development.......

10 X.

Implementation of the NRC Maintenance Rule.............

11 XI.

Reconciliation of ACRS Comments and Recommendations....

13 I

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t k e ii XII. ACRS Subcommittee Activities e Report of the ACRS Planning and Procedures Subcommittee Meeting Regarding the Conduct of ACRS Activities, Held on May 5, 1992......... 14 l XIII. Executive Session I e Reports to the Commission........................... 15 Memorandum......................................... 15 XIV. Summary / List of Follow-Up Matters........... 15 XV. Future Activities A. Future Agenda..................................... 17 B. Future Subcommittee Activities.................... 17 OFFICIAL USE ONLY SUPPLEMENT - XII. ACRS Subcommittee Activities - Appointment of ACRS Members [ SUPPLEMENT REMOVED - FOIA EX (b) (6) )

s ( Lii APPENDICES MINUTES OF THE 385TH ACRS MEETING i i MAY 6-9, 1992 I. Attendees j II. Future Agenda f III. Future Subcommittee Activities IV. List of Documents Provided to the Committee i i l \\ i i

"[s ' U%q'o w UNITED STATES

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!? t NUCLEAR REGULATORY COMMIMilON i 5 .I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS i o,, f WASHtNGTON, D. C. 20555 4r =,,,* \\ Revised: May 6, 1992 SCHEDULE AND OUTLINE FOR DISCUSSION 385TH ACRS MEETING MAY 6-9, 1992 Wednesday. May 6. 1992. Room P-110. 7920 Norfolk Avenue. Bethesda. Md. 1) 1:00 1:15 P.M. Ooenino Remarks by ACRS Chairman (Open) 1.1) Opening statement (DAW /SD) 1.2) Items of Current Interest (DAW /RFF) 2) 1:15 5:30 P.M. Poliev Issues for Certification of (3:00-3:15: Break) Evolutionary and Passive Nuclear Power Plant Desians (Open) 2.1) Discussion regarding proposed resolution of policy issues identified by the NRC staff regarding certification of evolutionary and passive power plant designs (CJW, et al./MME) 2.2) Meeting with representatives of NRC Staff, as appropriate 3) 5:30 6:00 P.M. ACRS Subcommittee Activities (Open) 3.1) Comments by ACRS Subcommittee Chairman regarding 4/21/92 meeting on the status of the IPE program and the development of Severe Accident Management Guidelines (WK/MDH) Thursday. May 7, 1992. Room P-110. 7920 Norfolk Avenue. Bethesda. Md. 4) 8:30 10:30 A.M. Containment Performance Criteria to Accommodate Severe Accidents (Open) 4.1) Comments by ACRS Subcommittee Chairman on the proposed NRC Advance Notice of Rulemaking (10 CFR Part 50) regarding a proposed rule on containment performance criteria to accommo-date severe accidents (DAW /MDH) 4.2) Meeting with representatives of the NRC staff and the nuclear industry, as appropriate

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j 2 10:30 10:45 A.M. BREAK 5) 10:45 12:00 Noon ACRS Subcommittee and Members' Activities (Open/ Closed) 5.1) Report of Subcommittee meeting on 5/5/92 regarding the GE ABWR control room design (HWL/CM/HA) 5.2) Report of Subcommittee meeting on 5/5/92 regarding international activities regarding use of computerized systems (HWL/JCC/HA) 5.3) Report of NRC team visit to discuss the Japanese GE ABWR control room design (JCC/HA) (Note: Portions of this session will be closed as necessary to discuss Proprietary Information and information provided in confidence by a foreign source.) 12:00 1:00 P.M. LUNCH 2:00 P.N. GE SinD11fied Boilina Water Reactor 6) 1:00 (Open/ Closed) 6.1) Report of ACRS Subcommittee Chairman regarding the test program proposed to support the SBWR design (IC/PAB) 6.2) Meeting with representatives of the NRC staff and GE (Portions of this session will be closed as necessary to discuss Proprietary Informa- .i tion applicable to this project.) 7) 2:00 3:00 P.M. Generic Issue B-56. Diesel Generator Reliability (Open) 7.1) Report by ACRS Subcommittee Chairman regarding proposed amendment to the NRC Station i Blackout Rule to fesolve GI B-56, l Diesel Generator Reliability (HWL/PAB) j 7.2) Meeting with representatives of the NRC staff and the nuclear industry, as appropriate 3:00 3:15 P.M. BREAK l l

'\\ 3 8) 3:15 5:15 P.M. Implementation of NRC Safety Goal Policy (Open) 8.1) Discuss proposed alternate plan to implement the NRC safety goal policy (DAW /MDH) 9) 5:15 6:30 P.M. Preoaration of ACRS ReDorts (Open) 9.1) Discuss proposed ACRS comments and recommendations regarding: 9.1-1) Advance Notice of Rulemaking regarding Containment Performance Criteria (DAW /MDH) 9.1-2) GI B-56, Diesel Generator Reliability (HWL/PAB) Friday, May 8. 1992. Room P-110, 7920 Norfolk Avenue, Bethesda, Maryland 10) 8:30 10:00 A.M. Definition of a "Laroe Release" (Open) 10.1) Report by ACRS Subcommittee Chairman regarding the NRC staff proposed definition of a "large release" of radioactivity in connection with implementation of the NRC Safety Goals (DAW /EGI) 10.2) Representatives of the NRC staff and the nuclear industry will participate, as appropriate 10:00 10:15 A.M. BREAK 11) 10:15 11:15 A.M. NRC Standard Review Plan Update and Develonnent (Open) 11.1) Comments by ACRS Subcommittee Chairman regarding the NRC staff i program to update and revise the NRC Standard Review Plan to better accommodate the review of future plant designs (CJW/EGI) 11.2) Briefing by representatives of the NRC staff 12) 11:15 12:15 P.M. Future ACRS Activities (Open) 12.1) Report of ACRS Planning and Procedures Subcommittee regarding proposed ACRS subcommittee and full Committee activities. 12.2) The status of arrangements for i multinational meeting of advisory bodies will be discussed. l l

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4 12:15 1:15 P.M. LUNCH 13) 1:15 3:15 P.M. Implementation of NRC Maintenance Rule (Open) 13.1) Comments by ACRS Subcommittee Chairman regarding proposed NRC Regulatory Guide to implement the NRC rule on nuclear power plant maintenance (10 CFR Part 50.65) (JCC/HA) 13.2) Meeting with representatives of the NRC staff and the nuclear industry, as approriate 3:15 3:30 P.M. BREAK 14) 3:30 4:00 P.M. Reconciliation of ACRS Comments and Recommendations (Open) 14.1) Discuss replies from the NRC Executive Director for Operations regarding staff reaction to ACRS comments and recomme.ndations regarding: 14.1-1) Prioritization of Generic Issues (ACRS report dtd. 3/11/92) (JEW, et al./SD) 14.1-2) Requirements for Full-Height, Full-Pressure Integral Systems Testing for the AP600 Passive Plant Design (ACRS report dated 4/20/92) (IC/PAB) 14.1-3) Additional items, as appropriate 15) 4:00 4:45 P.M. Subcommittee Activities (Open) 15.1) Report of Planning and Procedures Subcommittee regarding the conduct of ACRS activities (5/5/92 neeting)- (DAW /RFF) 15.2) Report of 5/6/92 Subcommittee meeting to discuss use of DAC in the regulatory process (JCC/MME) 16) 4:45 5:30 P.M. Accointment of ACRS Members (Closed) 16.1) Discuss the status of appointment of new members and the qualifications of candidates proposed for consideration (DAW /MFL)

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l 5 17) 5:30 6:30 P.M. Preparation of ACRS Reports (Open) 17.1) Discuss proposed ACRS comments and recommendations regarding matters discussed during this meeting, l including: 17.1-1) Definition of a "Large Release" (DAW /MDH) i 27.1-2) Implementation of NRC Maintenance Rule (JCC/HA) (Tentative) 17.1-3) Policy Issues for Certifica-tion of Evolutionary and t Passive Nuclear Power Plants (CJW,.et al./MME) 17.1-4) Implementation of NRC. Safety l Goal Policy (DAW /MDH) i Saturday. May 9, 1992. Room P-110, 7920 Norfolk Avenue. Bethesdgu j Mdx -18) 8:30 12:30 P.M . Preparation of ACRS Reports to the NRC 3 Recardinc: (Open) i 18.1) Discuss proposed ACRS reports to the-I NRC regarding items considered during this meeting (DAW, et al.) j 18.2) Discuss proposed ACRS reports regarding items considered but not completed at previous meetings as. l time and availability of information permit i 19) 12:30 1:30 P.M. Miscellaneous (Open)' 19.1) Complete discussion of items con-sidered during this meeting 1 t 4 r i 6 i i i

Federal i, ster / Vol. 57. No. 81 / Monday. Apr. /.1992 / No / ' material; the proposed revision would B. An estimate of the number of Representatives of the NRC staff will i require that specinc licenses be responses-30. participate, as appropriate. obtained for wrtain knports and exports

7. An estimate of the total number of 5:30p.m.-ops.rACRSSubcommitice of rs,dioactive waste.

hours needed to complete the Activities (Open}-he Committee wiII l Copies of the submtttal may be requirement or request: 5 Hours (10' hear briefings and discuss the status of inspected or obtained for a fee from the minutes per response)- assigned subcommftiee activities, l NRC Public Document Room.2120 L

8. An indication of whether section induding the status ofIPE reviews and Street. NW., (Lower Irvef), WashinFton. 3504[h). Public Law 96-511 applies:Not the status of the development of severe DC 20555.

applicable. Comments and questions may be

9. Abstrv:t-De NRC Form 277 affects accident management guidehnes.

directed by mail to the OMB reviewer-the employees oflicensees and Thursday. May 7,19e Ronald Mmsk. Paperwork Reduction contractors who have been granted an Protect (315H036 and 315>0027). NRC access authorization and require B 30 m-mum Cmtcirment OfDce of Information and Regulatory verification of that access authorization Perfor== Criterio to Accommodate Affairs.NEOB-3019, OfLce of in confunction with a visit to NRC or g.erdats (Oped-Tk Management and Budget. % ashington, another facihty. Com w21 review ed nph tk dvM e @poMMe% Comments may also be communicated inspec or fo a n the D W c na erstmon by telephone at 202/395.-306L NRC Public Document Room,2120 L """C""*'* The NRC efearance ofDceris Brenda Street NW. (lower Level), Washington, a cem date sem ents. )o. Shelton. 301/492-8132. DC 1045 a.mt-22Noorr ACRS S&mettee Acthke lOpen/ or[ 2N Closed}-ne Committee will discuss d ct mail to the B v ewer: For tk kkar Rer% hion Ronald Minsk. OfSce of Information and reports regardag the status d assigned Gerald F. Cranford. Regulatory Affairs, (3150-0051). NEOB_ subconnatttee activities, including DesignatedScamr @csolfor infctmoum 3019 Office of Management and Badget, design of the CEABWR control room Washington, DC 20503 and international activities related to trR Doc. 92.e714 %d 4-:4-c e 45 amj Commenta can also be submitted by use of digrtraed (computerized) i telephone at (202) 395-3084. instrumentstion and control systems in The NRC Clearance Officer is Brenda nudear plants. Jo Shelton. [301) 492.-8132. Portions of this session will be dosed Documents Crsd.Mg Reporting or' Deted at Dethesda Maryland this 54th day as necessary to discuss Proprietary Recordkeeping Requiremerrts-Office of Apnltihr Infonnchon apphcable to the issues of IAanagemerft and Budget Revtew For the Nockar Regulatory Commission. being disci.ased and informabon Acucy:Nucleat Regulato y GWdF. W prov ded in n! de ce by a foreign source. Co:nmbsslon. g 1p.m.-3puru Cenericissue B41 ACTl0* Notice of the OfLee of Management and Budget review cf [rR Doc. s2-ms md 4-u-e2*45 ami DieselCeneratarReliabihty (Open}-- Re Committee will review and information coIIection. comment on the proposed==A-t to i suuuAny:ne Nuclear Regulatory the Station hrt crat Rule to resolve GI Commission (NRC) has recent}y Advisory Comnettee or Reactor B-58, Diesel Generator Reliability. submitted to the OfBee of Management Sa """ WeeWng Agenda Representatives of the NRC staff and and Budget (OMB) for review the the nuclear trAn=try will participate, as followmg proposal for the coBection of in accordance with the purposes of appropriate. secuons29 and182b.of the Atomic information under the provisions of the Energy Act (42 USC. 2039,2232b), the 3:15p.m.-d-J5p.au CESimphfied Paperwork Reduction Act (44 USC. Advisory Committee on Reactor Boiling WaaerReactor(Open/ Closed}- chapter 35). Safeguards willhold a meeting on May The t'r-mittee will review and

1. Type of Submission, new. revision, 6.-9,1992, in Room P-110,7920 Norfolk comment on the proposed test program Avenue, Be'.hesda, Maryland. Notice of ior this standardrzed nuclear power or extensfore Extension.

2. Title of the informanon collection-this meeting was published in the p! ant. Representatives of the NRC staff Regeest for Visit or Access Approvah Federal Register en March 18.1992.

and CE Nw4 ear Eneqy will participate,

• 3 The form numberif appbcable:NRC as appropriate.

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4. How of ten the collection is J p e.-J:J5p.m.: Opening Remarks by as necessary to discuss Proprietary required: On occasion.

ACRSChairman(Open}-ne ACRS Inf rmation related to this matter.

5. Who wi!! be required or asked to Chairman will make opening remarks 4:15p.m.-4pm.flm;dementation of report Licensee and contractor and comment briaDy regarding items of NRCSafety Coo /Pohcy (Open}-The employees, who need to have access to current interest.

Committee willdiscuss proposed ACRS de ssified information or unescorted 1:15 p.m.-3p.m. and3:15p.m.-3:30 report on an alternate plan to implement access to an area requiring an access p.m.: Policy lasues for Certification of the NRC Safety Coal Policy. authonzation (security cicarance) in EvolutionaryandPassive Nuclear 6pa.-430p.auPreparation ofACRS conjunction with a visit to a facihty.The PowerPlant Des /ps (Open}-The Reports (Open}-ne Committee will NRC Form 277 mort be prepared and Committee will discuss policy issues discuss proposed comments and submitted to verify the individuals identified by the NRC staff regardmg recommedd= for ACRS reports secunty dearance and need-to-know for certification of evolutionary and passive regarding itema considered durmg this the visit. LWR power plant designs, meeting. i

15338 Feder:1 Reg.er / Vol. 57. No. 81 / Monday. April L.1992 / Notices t Friday. May 8.1.E quahfications of candidates proposed Further information regarding topics a30 a.m.-10 a.m.: Definition of a for appointment as Committee members. to be discussed. whether the meeting Targe Release"(Open)-The Portions of this session will be closed has been cancelled or rescheduled, the I Committee will review and report on as necessary to discuss information the Chairman's ruhng on requests for the proposed NRC staff definition of a large release of which would represent a opportunity to present oral statements i-release of radioactivity in connection clearly unwananted invasion of and the time allotted can be obtained by ' = with implementation of the NRC Safety personal privacy. a prepaid telephone call to the ACRS Coal Policy. Representatives of the NRC 2 P m.-2p.m.t ACRS Subcommittee Executive Director Mr. Raymond F. staff and the nuclear industry will Activities (Open)-The Committee will Fraley (telephone 301/492-8049). l participate, as appropriate. hear reports on and discuss assigned between 8 00 a.m. and 4:30 p.m. e.s.t. Jir15 a.m.-11:15p.m.:NRCStandard subcommittee activities. including the Dated: April 21,199* Review Plan Update andDevelopment ' planning and conduct of ACRS activities y, g i,, Program (Open)-ne Committee will and the use of design acceptance criteria hear a briefing by representatives of the (DAC)in the regulatory process. Advisory Committee Monegement off,cer. 2.m.-2.30 p.m.: Miscellaneous FhmmM NRC staff and discuss the NRC staff P """C*** program to revise the NRC Standard (Open)-ne Committee will complete Review Plan to better accommodate the discussion of items considered during this meeting and items that were not review of future plant designs. 17:15 a.m.-2125 p.m.r fbture A CRS completed at previous meetings as time OFFICE OF MANAGEMENT AND t Activities (Open)-The Committee will and availability ofinformation permit. BUDGET discuss anticipated ACRS subcommittee Procedures for the conduct of and activities and items proposed for participation in ACRS meetings were Office of Federal Procurement Polley consideration by the full Committee. published in Federal Register on p g p Plans for a multinational meeting of October 1.1991 (56 FR 49800). In advisory bodies will also be discussed. accordance with these procedurts, oral Systema 2:13 p.m.-115p.m.rlmplementation of or written statements may be presented AomcY: Executive Office of the NRCMaintenance Rule (Open)-The by members of the public, recordings President. Office of Management and Committee will hear a briefing by will be permitted only during those open Budget (OMB). Office of Federal 3 representatives of the NRC staff and portions of the meeting when a Procurement Policy. i discuss the status of the proposed in.1 script is being kept. and questions ACT10cc ne Office of Federal Regulatory Guide to implement this may be asked only by members of the Procurement Policy (OFPP)is requesting i Rule. Representatives of the nuclear Committee. its consultants, and staff. comments on a proposed policy on industry will participate, as appropriate. Persons desmng to make oral

• Procurement Data Systems."

l 3:30 p.m.-4:30 p.m.: Nuclear Power statements should notify the ACRS i }j Plant Opemting Experience (Open)-- Executive Director. Mr. Raymond F. sunsesARY:The Federal Government ) 1 The Committee will hear a briefing and Fraley, as far in advance as practicable spends almost $200 billion each year for 1 i discuss the AITinvestigation of so that appropriate arrangements can be products and services. Executive l 1 November 6.1992 event at the Millstone made to allow the necessary time during departments and agencies report l nuclear station that resulted from failu e the meeting for such statements. Use of selected data prrtaining to the nature 1 of a rehester drain line. Representatives still. motion picture, and television and magnitude of those purchases to the j ~ of the NRC staff and the licensee wi!! cameras during this meeting may be Federal Procurement Data System l j participate, as appropriate. limited to selected portions of the (FPDS).ne FPDS is the centralized I' ~ 4.30p.m.-Sp.m. Reconciliation of meeting as detennined by the Chairman. system that collects and disseminates ACRS Recommendations (Open}-ne Information regarding the time to be set procurement data to meet the needs of h Committee will discuss the replies aside for this purpose may be bbtainec Executive Branch. Congressional. and i received from the NRC Executive by a prepaid telephone call to the ACRS private sector users. Director for Operations regarding Executive Director prior to the meeting. This proposed Policy Letter i proposed NRC staff reaction to recent la view of the possibility that the establishes guidelines for the ACRS comments and recommendations. schedule for ACRS meetings may be management and control of procurement -j 5p.m.-6p.m.r Prepomfion ofACRS adjusted by the Chairrnan as necessary data systems to improve the accuracy. 1 Reports (Open)-The Committee will to facilitate the conduct of the meeting, timeliness, and completeness of

j discuss the proposed comments and Persons planning to attend should check procurement data. These policies were recommendations for ACRS reports with the ACRS Executive Director if developed to implement the regarding issues considered during this such rescheduling would result in major recommendations in OFPP's lune 1989 j /

meeting. inconvenience, report to Congress on the FPDS.The - d I have determined in accordance with Policy Letter also addresses needed f Saturday. May 9.1993 subsection 10(d) Public Law 92-463 tha t improvements in the governments's 4 i a30 a.m.-JJ a.m.: Prepamtion of it is necessary to close portions of this procurement management and contract ( ACRSReports (Open/ Closed)-The meeting noted above to discuss tracking systems.These provisions are 4 i j Committee will discuss the proposed Proprietary information applicable to in response to the recommendations l q reports to the NRC regarding nems the matters being considered in contained in an April 24.1991 report of considered during this meetmg. accordance with 5 U.S.C. 552(b)(4), the President's Council on Integnty and j

• i i Portions of this session will be closed information provided in confidence by a Efficiency on application controls for

j as necessary to discuss Proprietary foreign soarce per 5 U.S.C. 552b(c)[4).

Federal contract tracking systems. 1 Information. and information the release of which Rose recommendations also pertained JJ a.m.-12 Noon: Appointment of would represent a clearly unwarranted to improving data quality in agency i ACRSMembers (Open/ Closed)-The invasion of personal privacy per 5 U.S.C. systems that provide procurement Committee will discuss the 552b(c)(6). information to the FPDS. i \\ i -Y i ~

t vLnhB AU. MINUTES OF i 385TH ACRS MEETING MAY 6-9, 1992 The 385th meeting of the Advisory Committee on Reactor Safeguards I was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Md., on May 6-9, 1992. The purpose of this meeting was to discuss and take 3 appropriate action on the items listed in the attached agenda. The entire meeting was open to public attendance, with the exception of portions that dealt with the discussion of proprietary information related to the Simplified Boiling Water Reactor (SBWR) and selection of new Committee members. I A transcript of selected portions of the meeting was kept and is f available in the NRC public Document Room. (Copies of the j transcript are available for purchase from Ann Riley & Associates, 5 Ltd., 1612 K Street, N.W., Washington, D.C. 20006.) j ATTENDEES 1 l ACRS Members: D. Ward (Chairman), P. Shewmon (Vice Chairman), I. l

Catton, J.

Carroll, W.

Kerr, H. Lewis, C. Michelson, T.

Kress, J.

E. Wilkins, and C. J. Wylie i I. Chairman's Report (Open) I Note: Mr. R. F. Friley was the Designated Federal Official for this portion of the meeting. i \\ Mr. D. Ward, ACRS Chairman, opened the meeting at 1:00 p.m. and i discussed the day's schedule for the meeting. ] II. Poliev Issues for Certification of Evolutionary and Passive l Nuclear Power Plant Desians (Open) i l Note: Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting. i The Committee discussed the staff's positions, recommendations, and resolution schedules for the policy issues identified by the staff i regarding certification of light water reactor power plant designs. the staff had identified several policy and significant technical issues pertaining to the design in a draft SECY paper, dated February 7, 1992. Representatives of the staff and EPRI were present and answered questions regarding the items. ~ t ) B

i i 385th ACRS Meeting Minutes 2 i conclusions The Committee completed a report to Mr. J.

Taylor, Executive Director for Operations, regarding eight issues applicable to passive and evolutionary plants.

The Committee will pursue nine more of the policy issues applicable to passive plants. Assignments were made to ACRS members for discussion at the June 1992 meeting. The Committee expects to write a report on these policy issues for passive plants at its l July 1992 meeting. t III. Recorts on ACRS Subcommittee and Members Activities (Open) i a) Recort on the Joint Meetino of the IPE and Severe Accidents Subcommittees Held on April 21, 1992 Note: Mr. M. D. Houston was the Designated Federal Official for this portion of the meeting. j Dr. Kerr, Chairman of both the Individual Plant Examinations and Severe Accidents Subcommittees, summarized the meeting on April 21, 1992, during which the staff and NUMARC presented status reports on the IPE and Accident Management Programs. He indicated that, to I date, 12 IPE submittals have been received and only 1 staff review has been completed. He specifically noted two areas, maintenance l proguams and the Station Blackout Rule, that could be studied for correlation with core damage frequency results. He requested that the Committee forward some comments on IPE insights to the staff, j and the Committee agreed to consider his proposal at the June meeting. In regard to the Accident Management Program, Dr. Kerr noted that -the staff had no clear definition of an accident. This leads to duplication of effort in developing emergency operating procedures and accident management procedures. He indicated that a more precise definition of an accident might avoid this duplication. The members discussed the status of the IPE Program and the development of the severe accident management guidelines, as discussed at the meeting. The following special concerns resulting from the April 21st Subcommittee meeting were mentioned: Executive summaries from different studies are showing different views with regard to adding water to a molten core and for steam explosions. i The Subcommittee was told that the staff is not doing any ^ work on accident management for advanced reactors. No "research need" has been identified at this time.

'\\ 1 385th ACRS Meeting Minutes 3 Uncertainties can be eliminated by reducing the events that are uncertain, to those events that are known, i.e., plants should be designed to eliminate the uncertain i events. i t conclusions No action was taken on this matter at this meeting. The Committee expects to forward comments on the use of IPE results to the EDO during the June 4-5, 1992 Committee meeting. b) pecort on the Subcommittee Meetina Recarding the GE ABWR i Control Room Desion. Held on May 5, 1992 Note: Mr. H. Alderman was the Designated Federal Official for this portion of the meeting. Dr. Lewis summarized the May 5, 1992 joint meeting of the Subcommittees on Computers in Nuclear Power Plant Operations and on Advanced Boiling Water Reactors. The main issues were:

1. Validation and Verification (V and V) of software

2. Assurance against Malfunction There was discussion of whether GE will be able to do a V and V with formal nath logic (GE has made a commitment to do this for the

{ ABWR), or only with symbolic logic by verifying what is in the program. Dr. Lewis pointed out that V and V has a different meaning to non-nuclear type computer people than to the nuclear industry-people. He noted the possibility of miscommunication, e.g., IEEE uses terms l not used in computer classes. Another matter of concern to him is I that testing and design philosophy for the nuclear area has always been with hardware. He said that failures are-different for software, since software always repeats exactly, while hardware does not always repeat exactly. Mr. Michelson expressed concern that it is now not clear to him i what information regarding the ABWR digital control and protection systems will be available in the Final Safety Evaluation Report at the time the staff and the Committee are expected to make their final determination on the design. He would-like to know what information will be available with regard to these items in the Final SER. t Dr. Lewis suggested that the best way the ACRS can help the staff { at this time is to help the staff determine and develop the tools they will need in this area for future design reviews. N

\\ l 385th ACRS Meeting Minutes 4 i Conclusions i This was an information briefing. I c) Report on the Joint Meetino of Subcommittees on Computers in l Nuclear Power Plant Operations and on Human Factors. Held on { May 5. 1992 ~ Note: Mr. H. Alderman was the Designated Federal Official for this portion of the meeting. a Mr. Carroll briefed the Committee on the May 5, 1992 meeting, I noting that there would be a separate Design Acceptance Criteria { (DAC) for the control room of the GE ABWR. Work will be based on j the Japanese design, with which the control boards for the Japanese plant have been designed (the technology now being 10 years old). With regard to whether the staff gained any information useful'for 4 the ABWR review from the long experience they have had with the l Combustion Engineering digital computers, Mr. Newberry, NRC, said i the key lesson was that an independent" V and V should be required I by the vendor. i t Conclusions i i This was an information briefing. No ACRS action was taken at this =eeting. l d) Report on Subcommittee Meetino on Computers in Nuclear Power i Plants Concernino International Computer Hardware and Software 1 Activities. Held on May 5. 1992 s '. Note: Mr. H. Alderman was the Designated Federal Official for this portion of the meeting. j It was noted that Mr.

Russell, NRC staff, had briefed the j

Subcommittee on his recent trip to Japan. Members of the staff had -- discussed French and Canadian computer. activities, and Mr. - l Beltracchi,

RES, discussed his international contacts in the computer field.

During the Subcommittee meeting, a representative from a utility in 1 Finland ~ discussed their experience replacing.the.three Loviisa. j PWRs' process computers while the plant was operating. i Dr. Kerr was impressed with the fact that the NRC is making a j reasonable effort to find out what is going on internationally; j however, he did not get a feel for what the staff is doing with the information they are getting. j 1 ~ ..J

.c 385th ACRS Meeting Minutes 5 Conclusions i This was an information briefing, i e) Trio Recort by ACRS Member J. Carroll on His Trio to Japan Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting. i Mr. Carroll reported on his recent trip to Japan, noting that he acco=panied an NRC team to: Look at control room design for the K6/K7 plants. e Learn about test and evaluation program, i.e., mockups simulators, and prototypes. Check on the basis for the key features of the ABWR control room design. Mr. Carroll indicated that he was impressed with what he saw. He passed out a detailed trip report to the members providing details of his visit. conclusions Mr. Carroll suggested that it would be advisable to invite the l Japanese to a future meeting with the Committee, but recommended that the Committee should not plan a future trip to visit Japan at this time. IV. Containment Performance Criteria to Accommodate Severe Accidents (Open) i Mr. M. D. Houston was the Designated Federal Official for this portion of the meeting. Mr. Ward, Chairman of the Containment Performance Subcommittee, said that the Advanced Notice on Proposed Rulemaking (ANPR) to 10 CFR Part 50 was the second phase to decouple siting from plant design. He noted that the Committee had previously reviewed the first phase that involved moving sections of 10 CFR Part 100 to Part 50 and changes to the source term. He indicated that the ANPR was closely related to the containment design criteria proposed by the Committee in their May 17, 1991 report. Dr. T. King, RES, discussed the ANPR on Severe Accident Performance Criteria for Future LWRs. As background, he discussed the overall i plan to decouple siting from design that included plant performance 1 criteria related to severe accidents. He indicated that the fcilowing phenomena should be considered in the ANPR: I

9 385th ACRS Meeting Minutes 6 l Hydrogen generation and combustion / detonation e Fuel-coolant interaction Core-concrete / structure interaction e High-pressure melt ejection e over-pressure /over-temperature caused by decay-heat / chemical e energy containment bypass e Dr. King discussed the three alternatives presented in the ANPR. These are summarized as follows:

• Alternative 1:

Prescriotive - Hardware-Oriented Rule - Specify as much as possible those severe accident design features that future LWR designs should include - Limits analysis required by designer - Based upon approach and criteria developed in review of evolutionary LWR designs and the EPRI Requirements Document e Alternative 2: Nonorescriptive - Phenonena-Oriented Rule I - Specify severe accident phenomena which must be considered in the design - Designer would provide analysis and propose r design features judged necessary - Based upon severe accident phenomena considered important in current and evolutionary designs 5

• Alternative 3:

ACRS Proposal - May 17, 1991 ACRS letter - New or revised General Design Criteria Dr. King indicated that the ANPR would be issued for public comment and would apply to the passive plants and other future LWRs but not to the currently designed evolutionary plants. The performance criteria for evolutionary plants would be part of the certification rulemaking proceedings on these plants. The staff would strive for consistency in these criteria between the evolutionary and future LWRs. The Committee discussed in detail the severe accident phenomena to ) be considered in the ANPR and restated their preference for i Alternative 3. i l

385th ACRS Meeting Minutes 7 Conclusions The Committee issued a report, dated May 14, 1992, to the EDO on the advanced notice for proposed rulemaking on severe accident plant performance criteria for future LWRs. V. Review of Test Procram in Succort of the GE Sinolified Boilina Water Reactor Desian Certification (Open/ Closed) Note: Mr. P. Boehnert is the Designated Federal Official for this portion of the meeting. The Committee heard presentations from representatives of the General Electric Co. (GE) and the NRC staff on the status of the NRC staff's review of the GE test and analysis program in support of the certification effort for the Simplified Boiling Water Reactor (SBWR) passive plant design. Key points noted included: Dr. Catton, Thermal Hydraulics Phenomena Subcommittee Chairman, noted that the Subcommittee met to review this matter on April 23, 1992. He described the novel features of the SBWR passive plant design. The current schedule calls for the NRC staff to certify the design in 1996. NRR has put two questions to the ACRS concerning its review of the GE SBWR test program: a) Is full-height, full-pressure integral system testing (IST) needed to support SBWR design certification? b) Is there a need for low-pressure IST for same? Dr. Catton said that he believes the Committee's review of e this matter can be concluded during its June meeting. The T/H Phenomena Subcommittee will hold another meeting on June 2nd to explore additional information relevant to the above questions. The GE representative acknowledged that GE needs to provide both the Subcommittee and the NRC staff with more details relevant to the key SBWR design parameters and the test programs. This information will be provided prior to the June 2nd Subcommittee meeting. GE discussed its testing and analysis approach in support e of the SBWR certification effort. The so-called Passive Containment Cooling System (PCCS) is the major technologi-cal innovation on this design. As such, it is the main focus of the test programs. The TRACG code will be used to conduct the necessary analyses; this code will be exten-sively documented for this use.

9 385th ACRS Meeting Minutes 8 A summary of three items characterized as " key issues" by e the GE representative was presented. These issues are: stability, inventory control, and containment decay heat removal for the PCCS. The major issue of contention between GE and NRR at this time is whether the results from l full-height / low pressure IST planned at the Swiss PANDA facility need to be incorporated into the certification effort, or can, as GE maintains, be considered " confirmatory". NRR noted the following three major concerns regarding the e GE test programs: a) Additional testing is needed to qualify the performance of the squib valves used to activate the PCCS. b) GE needs to provide additional information i.- order to address the issue of the core-power-stability of the SBWR design. c) Test data and analysis is needed to ensure that the coupling of the RCS and containment performance is sufficiently unde.rstood, particularly for accident / transient conditions. Note: NRR addressed the two questions noted above for which it is soliciting the Committee's comment. These questions (and the preliminary staff 7 positions in parentheses) are: (1) Is full-height / full-pressure integral system testing (IST) I required for this design (probably not)? and 2) Is there need for additional IST to demonstrate the PCCS concept (yes, and it appears that testing planned by GE at the Swiss PANDA facility should address NRR's concerns in this regard)? Conclusions t The Committee deferred further action on this matter to its June 1992 meeting. VI. Generic Issue B-56, Diesel Generator Reliability (Open) Note: Mr. P. Boehnert was the Designated Federal Official for this [ portion of the meeting. Dr. Lewis introduced this matter to the Committee. He noted that the NRC staff had developed a proposed amendment to the Station { Blackout (SBO) Rule at the behest of the Commission to resolve the t

385th ACRS Meeting Minutes 9 issue of ensuring adequate reliability for the emergency diesel generators (EDGs) used to provide emergency ac power at nuclear power plants. The Committee had reviewed and commented on the proposed amendment during its December 1991 meeting. Dr. Lewis noted that the Committee disapproved issuance of the proposed amendment, regarded as being unnecessary. A joint meeting of the PPA / Control and Electrical Power Systems Subcommittees was held on April 22, 1992. The purpose of the meeting was to discuss the proposed amendment to the SBO Rule that was about to be issued. [ Note: The proposed amendment to the SB0 Rule was published for public comment in the Federal Register on April 21, 1992.] Dr. Lewis noted that the Subcommittee heard presentations from the NRC staff and NUMARC. The Subcommittee also heard from Dr. N. Singpurwalla, an expert in statistics, who is consulting for the ACRS in this matter. In addition, the ACRS was provided, by NUMARC, with a set of data from INPO that details the performance of all nuclear industry EDGs for the years 1988-1990. In brief, Dr. Lewis outlined the concern he has with the proposed amendment to the Rule, as follows: the amendment mandates a demonstration of the EDG reliability. The problem is that given the small number of failures seen by the fleet of EDGs, one cannot determine the reliability of a given diesel on a statistically acceptable basis; i.e., the number of failures seen per diesel per year (1 to 3) are not statistically significant. Dr. Lewis introduced Dr. Nozer Singpurwalla to the Committee. He noted that Dr. Singpurwalla has been investigating this matter from a statistical basis. At Mr. Carroll's request, Dr. Singpurwalla made a brief presentation to the Committee on this latter effort, concluding that one could likely determine the " bad actors" in the population of the EDGs from statistical analyses. Mr. A. Serkiz (NRC-RES) made some comments in clarification of the provisions of the proposed amendment to the Rule. As a result of questions from the Committee, Mr. Serkiz indicated that the staff believes the trigger values chosen provide an indication that a given diesel's reliability has degraded to an unacceptable value. Conclusions The Committee completed a report to Chairman Selin on this matter, which included a recommendation that the proposed amendment to the Rule be set aside in favor of a valid statistical approach to the monitoring of EDG reliability.

385th ACRS Meeting Minutes 10 ) VII. Irelerientation of NRC Safety Goal Policy (Open) Note: Mr. M. D. Houston was the Designated Federal Official for this portion of the meeting. Mr. Ward, Chairman of the Ad Hoc Working Group on the Safety Goal, presented a first reading of a proposed ACRS report on the implementation of the Safety Goal Policy. An implementation plan was described that would be an alternative to the staff's plan given in SECY-91-270. Conclusions Members were asked to provide their comments for further consideration of this matter during the June ACRS meeting. VIII. Definition of a "Larce Release" (Open) Note: Mr. M. D. Houston was the Designated Federal Official for this portion of the meeting. The Committee heard presentations from representatives of the NRC staff on their proposal for the definition of the term "large release" to be used in conjunction with the Safety Goal Policy. Due to difficulty in establishing a quantitative definition, the staff is now recommending a qualitative large release definition - being any release from an event involving severe core damage, reactor coolant system pressure boundary f ailure, and early failure or significant bypass of the containment. Conclusions The Committee agreed with the staff proposal to use a qualitative definition for a "large release" on a trial basis, and provided a report to Chairman Selin on this matter. IX. NRC Standard Review Plan Uodate and Develcoment (Open) Note: Mr. E. Igne was the Designated Federal Official for this portion of the meeting. Representatives of the NRC staff briefed the Committee on the need for the NRC to update its Standard Review Plan (SRP), the major reason being that there is inconsistent documentation of the criteria basis, but, also, corporate memory needs to be captured with the high potential staff turnover in the near future. A 1 Commission directive calling for this update has been issued. l ) i i i

385th ACRS Meeting Minutes 11 It was noted that state-of-the-art electronic media will be employed between NRC and PNL, NRC's contractor for this update, to rapidly transmit information, including graphics. This will be on the local area network, LAN, and will be available to ACRS. Ms. Pam Kruzic, IRM, should be able to provide access information. The SRP update program (SRP-UDP) objectives are to update the SRP for present LWRs as well as future reactor designs (e.g., advanced reactors, CANDU, LMR, etc.), provide systematic documentation, and provide for long-term maintenance. Mr. Gillespie stated that until mid-1993 the staff will be in the midst of its integration process of digesting all of the existing SRP materials, sorting the information, and determining what is i needed in the SRP-UDP. He asked the ACRS to provide suggestions on improving the format of the SRP-UDP for user convenience. Conclusions This was an information briefing only. No ACRS action was taken at this time. i X. Imolementation of NRC Maintenance Rule (Open) Note: Mr. H. Alderman was the Designated Federal Official for this portion of the meeting. i The Committee heard presentations by representatives of the NRC staff and by NUMARC on this matter. NUMARC indicated that they were proceeding in parallel with the NRC in the development of a maintenance guidance document. Either the NUMARC or the NRC document will be selected as the final maintenance standard. The decision as to which document is to be selected as a final maintenance standard will be made in June 1992. The staff will present the final guidance document to the ACRS in August 1992, and at that time the document will be sent out for public comment. It i is expected that the staff will brief the committee on the proposed final version of the regulatory guide in March 1993. The guide is scheduled to be issued in June 1993. NUMARC Presentation Mr. Walter Smith,

NUMARC, discussed the industry maintenance guidance.

He noted the following: The NUMARC document, that was issued on March 31, 1992, had a large amount of industry input. He noted that the language and terminology of this document are better understood by utilities than by the NRC. I

• y o

385th ACRS Meeting Minutes 12 NUMARC plans to conduct a verification and validation = program with the industry guideline. This program, to be completed in December 1992, will be based on plants of similar size and vintage. This will provide a method to measure whether or not this guideline, if implemented, would achieve consistent results. NUMARC believes that in the area of emergency operating e procedures (EOPs) many utilities include equipment, methodologies, and techniques that are not normal alignments or normal applications of the system to perform its function. The staff's position is that if the equipment is identified in the EOPs, it is within the scope of the maintenance rule. Between 13 and 20 percent of all f ailures are maintenance e related. All the systems that could potentially contribute to core damage will be evaluated relative to their actual contribution to damage frequency. If the performance is acceptable, then you would just continue to monitor the system performance. If the performance is not acceptable, then corrections would have to be made to make the system performance acceptable. e The performance of systems will be evaluated against established goals. NRC Staff Presentation Mr. J. Heltemes, Deputy Director, Office of Research, was the main presenter for the NRC staff. He noted that the Commission passed a performance-based maintenance rule, 10 CFR 50.65, in June 1991. It was put in the Federal Register in July 1991, and will be effective July 10, 1996. During his presentation the following l remarks were made: The purpose of the rule is that licensees monitor the performance or condition of certain structures, systems, and components (SSCs) against licensee-established goals in a manner sufficient to provide reasonable assurance the SSCs are capable of performing their intended i function. The scope of the rule covers all safety-related SSCs. The rule also states that non-safety-related SSCs are under the rule if, 1) They are used in the emergency operating procedures, 2) failure could prevent safety related SSCs from fulfilling their intended function, or L

4 385th ACRS Meeting Minutes 13

3) failure could cause a scram or an actuation of a safety system.

Licensee-established goals are under the control of the e licensees. They will not be reviewed by the NRC. The goals may be performance oriented, i.e reliability or availability, or condition oriented, i.e. parameters. If preventive maintenance programs are sufficient, no goals and no specific monitoring against goals are required. The NRC staff agrees in principle with the NUMAFtC-suggested change to increase the surveillance period from annually to every refueling outage or a maximum of two years. T. Foley, NRR, commented that they have been requested by the Commission to develop interim inspection guidance for inspectors for use until such time as the Rule is implemented. The proposed guidance will be sent out for public comment. In response to questions, Mr. Foley said he thought the maintenance rule woulii reduce the number of scrams and the number of safety system actuations. conclusions I 1 l This was an information briefing. No ACRS action was taken on this matter at this meeting. - XI. Reconciliation of ACRS Comments and Recommendations (Open) { The Committee discussed the staff's response to the Committee's letters on the need for integral systems high pressure testing for the Westinghouse AP600 plant. Dr. Catton noted that he had met with some of the Commissioners and had made the following remarks: The staff needs more analytical capability with regard to the need for high pressure testing. If the RELAPS/ MOD 3 Code is modified to support the ROSA IV test program, experience has shown it takes 3-5 years experience to make the code dependable. He questioned whether time would allow for the modification and use of such a code? 1

385th ACRS Meeting Minutes 14 i If the biggest share of uncertainty lies in the low pressure area, the NRC should be spending its money for research at a low pressure facility. Conclusion The Committee will look at this matter again before a final decision is made on the use of the test facility to be used and the need for the codes. XII. ACRS Subcommittee Activities (Open/ Closed) Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting. Rapprt of the ACRS Plannino and Procedures Subcommittee Meeting Recardina the Conduct of ACRS activities, Held on May 5, 1992 Mr. Ward summarized the discussions and recommendations of the May l 5, 1992 Planning and Procedures Subcommittee meeting, as follows: l a) Accointment of ACRS Members (Closed) Contained in Official Use Only Supplement to Minutes. b) Multilateral International Meetinc of Adviserv Groues (Open) The Committee agreed to a proposed schedule for the upcoming May 26, 1992 Ad Hoc Working Group Meeting with German RSK members. This meeting is being held at the request of the RSK to discuss topics suggested by them regarding containment design / performance to accommodate severe accidents and related matters, as well as to discuss a multilateral meeting of advisory committees. Several members of the Committee agreed to attend the meeting arj ts lead topics of discussion. c) Imolementation of Chairman Selin's Succestions for Future Committee Activities (Open) The Committee agreed with the recommendations of the Planning and Procedures Subcommittee that written lists of work items on which the Committee is working / planning to work should not be provided to the Commission as a mechanism to reach agreement regarding conduct 4 of long-range Committee work assignments, but, instead, Mr. Ward should periodically discuss the active working assignments with j Chairman Selin. Subcommittees should continue to work on these matters as planned (e.g., ACRS Key Technical Issues). u i

385th ACRS Meeting Minutes 15 i The Committee encouraged Mr. Michelson to continue to work on the ACRS Key Technical Issue No. 3, on separation and independence requirements for redundant safety trains. d) Subcommittee Meetina Minutes (Open) The Committee endorsed the guide written by Dr. Siess for writing and issuing minutes of meetings. New ACRS members should be given copies of the guide. Mr. Fraley agreed to promulgate Dr. Siess' guide for use by the staff, etc. XIII. Executive Session (Open) t The Committee co=pleted the following Reports and Memorandum as noted. REPORTS e Feliability of Enercency AC Power at Nuclear Power Plants (Report to Chairman Selin, dated May 19, 1992) Definition of a Larce Release for Use With the Safetv Goal Policy (Report to Chairman Selin, dated May 13, 1992) Advanced Notice of Proposed Rulemakina on Severe Accident Plant e Performance Criteria for Future LWRs (Report to Mr. James M. Taylor, Executive Director for Operations, dated May 14, 1992) i l Issues Pertainina to Evolutionary and Passive Licht Water e Reactors and their Relationship to Current Reaulatory i Recuirements (Report to Mr. James M. Taylor, Executive Director for Operations, dated May 13, 1992) i MEMORANDUM SECY-92-153. Verification of Seismic Adecuacy of Mechanical and e Electrical Ecuionent in Older Operatina Nuclear Power Plants. Unresolved Safety Issue (USI) A-46 (Generic Letter 87-02) (Memorandum to James M. Taylor, Executive Director for Operations, from Raymond F. Fraley, Executive Director, ACRS, dated May 13, 1992) XIV.

SUMMARY

/ LIST OF FOLLOW-UP MATTERS 1

Mr. Michelson requested that GE provide him details on the e design, performance and testing associated with the squib valves used to actuate the passive containment cooling system (PCCS) for the proposed GE Simplified Boiling Water Reactor. (Mr. Boehnert has the follow-up on this item.) j

i k 385th ACRS Meeting Minutes 16 l t Mr. Michelson expressed concern regarding the i= pact of the e reactor water cleanup system on the ex-containment LOCA { event for the proposed GE Si=plified Boiling Water Reactor. NRR agreed that this system needs to be evaluated with this event in mind and they committed to do so. (Mr. Boehnert has the follow-up on this item.) e Mr. Gillespie agreed to provide the Committee with copies of a milestone chart on the development and planning accomplishments of the Standard Review Plan - Update } Program. (Mr. Igne has the follow-up on this item.) Committee members suggested that an ACRS Fellow be assigned 4 e to qualitatively evaluate the IPE data base that comes out i of Brookhaven National Laboratory's work. (Dr. Savio has the follow-up on this item.) Mr. Wylie said he would contact someone at EPRI to see what e the EPRI Requirements Document says, if anything, with l regard to design features to facilitate decommissioning. i (Dr. El-Zeftawy has the follow-up on this item.) The Committee agreed to drop, for now, the consideration of 3 e j a trip to Japan for ACRS members to discuss the ABWR. l The comments made by Chairman Selin at previous ACRS 4 e e meetings concerning selection of the most knowledgeable future ACRS members that may have possible conflicts of e j interests should be made available to those in the staff l i that will be reviewing the prospective = embers with regard to their backgrounds. (Mr. Fraley has the follow-up on i i this item.) i The Committee endorsed the Guide that Dr. Siess provided s e to the Committee concerning the preparation of ACRS subcommittee meeting minutes. New ACRS members should i be given copies of this Guide. (Mr. Fraley has the i follow-up on this item.) i The Committee decided not to send a list of items it wishes 4 o to work on to the Commissioners for consideration, similar to what the ACNW does. The Committee Chairman should j discuss these matters with the Chairman of the Commission. (Mr. Fraley has the follow-up on this item.) i Scott Newberry, NRC staff, will provide the Committee with i e I ongoing lists for information of computer-related meetings ] scheduled to be held in this country and abroad for information. (Mr. Alderman has the follow-up on this { item.) 1

1 385th ACRS Meeting Minutes 17 1 Dr. Catton would like to know whether enough is known about e igniter locations in containments, such that they will not act as detonators. (Mr. Houston has the follow-up on this item.) It is not clear exactly what will be included in the e staff's Final Safety Evaluation Report for the ABWR regarding the digital control and protection systems. Therefore, the staff should tell the Committee how it will make its final determination for the ABWR based on the information that is to be provided. (Dr. El-Zeftawy has the follow-up on this item.) f Mr. Gillespie said he would consider an NSSS proposal to e rearrange the Standard Review Plan order of chapters so that they are more appropriate for the licensees. (Mr. Igne has the follow-up on this item.) l XV. FUTURE ACTIVITIES (Open) A. Future Acenda The Committee agreed to a tentative schedule for the 386th, June 4-i 5, 1992 ACRS meeting as contained in Appendix II. I k B. Future Subcommittee Activities A list of future ACRS Subcommittee meetings was distributed to the i Committee members (Appendix III). The meeting was adjourned at 11:30 a.m., Saturday, May 9, 1992. J i 1 1 )

( s o U APPENDICES MINUTES OF THE 385TH ACRS MEETING MAY 6-9, 1992 I. Attendees II. Future Agenda III. Future Subcommittee Activities IV. List of Documents Provided to t'? Cormittee 1 i j l i i

( o. APPENDIX I MINUTES OF THE 385TH ACRS MEETING MAY 6, 1992 EUBLIC ATTENDEES NRC ATTENDEES Wednesday, May 6, 1992 l P. W. Marriott, GE Nuclear Energy R. VanHouten, SECY l J. D. Trotter, EPRI R. Borchardt, NRR J. A. Beard, Halliburton NUS W. Travers, NRR Russ Bell, NUMARC J. Giiter, NRR M. Case, NRR M. Taylor, OEDO E. Rcdrick, RES Thursday. May 7, 1992 John Trotter, EPRI D. Trimble, OCM/JC Theresa Meisenheimer, SERCH-Bechtel G. Kelly, NRR Colleen Amoroso, Halliburton NUS B. Zalcman, NRR Joan Butler, NUMARC R. VanHouten, SECY Greg Brown, Stone & Webster E. Throm, NRR David Leaver, Tenera/EPRI C. Ader, RES L. Zerr, STS M. Case, NRR M. Phillips, Newman & Holtzinger J. Monninger, NRR A. Marion, NUMARC C. McCracken, NRR G. Rombold, NUMAI1C J. Y. Lee, NRR Bob Helfrich, Winston & Strawn A. Munvera, AEOD Robert Draper, Winston & Strawn T. Gody, NRR Jan McGregor, Winston & Strawn M. Taylor, OEDO Russ Bell, NUMARC S. Newberry, NRR A. Levin, NRR A. Thadani, NRR W. Travers, NRR A. Serkiz, RES 0. Chopra, NRR F. Rosa, NRR G. Sege, RES l l

'd l i j 385th ACRS Meeting Minutes I-2 Appendix I, Attendees (Continued) ) PUBLIC ATTENDEES NRC ATTENDEES Friday. May 8, 1992 Alice Cummings, SERCH Licensing-Bechtel D. Trimble, OCM/JC Charles Willbanks, Halliburton NUS R. Van Houten, SECY Stephen Additon, Tenera J. Ridgely, RES John Butler, NUMARC M. Case, NRR John Trotter, EPRI C. Ader, RES i Lloyd Zerr, STS T. King, RES John Ciccone, NUMARC M. Taylor, OEDO { David Teague, Winston & Strawn F. Gillespie, NRR i M. Phillips, Newman & Holtzinger T. Gody, NRR 1 Tom Ippolito, SEA S. Bajwa, NRR 1 Gilbert Zigler, SEA G. Barber, NRR l Warren Hall, NUMARC O. Rothbey, RES i Walt Smith, NUMARC R. Baer, RES Patrick Harr, Newman & Holtzinger J. Heltemes, RES S. J. Patterson, Newman & Holtzinger T. Foley, NRR Les Toth, Gasser Associates J. Boardman, AEOD 1 C. Johnson, RES d: e I l

4 APPENDIX II MINUTES OF THE 385TH ACRS MEETING MAY 6-9, 1992 FUTURE AGENDA Tentative Schedule for the 386th ACRS Meetina, June 4-5, 1992 A. Iglementation of NRC Safety Goal PolicJ - Discuss proposed ACRS recommendations for an alternate plan for implementation of the NRC quantitative safety goal policy. Representatives of the NRC staff will participate, as appropriate. B. Certifiqation of Evolutionary and Passive Plant Desions - Discuss policy issues associated with the certification of evolutionary and passive standardized plant designs. Representatives of the NRC staff and the nuclear industry will participate, as appropriate. C. Fitness for Duty - Review and report on proposed revisions to 10 CFR Part 26, Fitness for Duty Programs. Representatives of the NRC staff and the nuclear industry will participate, as appropriate. D. EPRI Reauirements for Passive Licht Water Reactors - Discuss committee plans for reviewing the proposed EPRI requirements for passive light water reactor designs. E. GE Simplified Boilina Water Reactor - Review and report on the test program proposed for this standardized nuclear plant. Representatives of the GE Company, and the NRC staff wi] l participate, as appropriate. F. Implementation of Revised 10 CFR Part 20, Standards for Protection Acainst Radiation - Review and comment on proposed final regulatory guides to implement the revised 10 CFR Part 20, Standards for Protection Against Radiation. Specific guides to be considered include RG 8.7, Revision 1, Recording and Reporting Occupational Exposure, and RG 8.N.6, Planned Special Exposures. G. ACRS Subcommittee Activities Reports and discussion regarding the status of assigned subcommittee activities, including matters related to use of Design Acceptance Criteria in the Certification Process, qualifications of candidates for appointment to the Committee, and conduct of Committee activities. H. Proposed Resolution of Generic Issue 23. " Reactor Coolant Pump Seal Failures" - Briefing by and discussion with the NRC staff regarding the status of the NRC staff's effort for resolving Generic Issue 23. Representatives of the nuclear industry will participate, as appropriate.

i APPENDIX III MINUTES OF THE 385TH ACRS MEETING MAY 6-9, 1992 FUTURE SUBCOMMITTEE ACTIVITIES May 9, 1992 Recional Procrams, May 20, 1992, Region V Office, 1450 Maria Lane, Walnut Creek, CA (Houston), 8:30 a.m. The Subcommittee will discuss the activities of the NRC Region V Office. Attendance by the following is anticipated, and reservations have been made at the Embassy Suites (510/934-2500), 1345 Treat Blvd., Walnut Creek, CA for the night of May 19: Shewmon Lewis Catton Ward carroll Wilkins Kerr Wylie Kress Joint Materials and Metallurev/ Advanced Reactor Desians, May 21,. l

1992, Holiday Inn Financial District, 750 Kearny Street, EAD Francisco. CA (Houston), 8:30 a.m.

The Subcommittees will discuss the application of the high temperature structural materials in the Advanced Liquid-Metal Reactor (ALMR). Attendance by the following is anticipated, and reservations have been made at the Holiday Inn Financial District (415/433-6486) for the nights of May 20 and 21): Shewmon Kress Ward Lewis carroll Wylie Catton Snow Kerr Ad Hoc Workino Groun on Multinational Meetinc,[gLpSED), May 26, 1992, 7920 Norfolk Avenue, Bethesda, MD (Quittschreiber), 8:30 a.m., Room P-110. The Ad Hoc Working Group will hold a preliminary discussion with some members of the German Advisory Committee, RSK, to discuss some matters of general interest and to develop plans i j for the Second International Quadripartite meeting of advisory groups to be held in late 1992 or 1993. Attendance by the following is anticipated, and reservations have been made at the Bethesda Ryatt Regency Rotal for the nights of May 25 and 26: Wilkins Lewis Catton Shewmon Kerr Ward Kress Wylie

a i 2 Severe Accidents, May 27, 1992, 7920 Norfolk Avenue, Bethesda, MD (Houston), 8:30 a.m., Room P-110. The Subcommittee will discuss the revision to NUREG-1365, Severe Accident Research Program Plan. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of May 26: l Kerr NONE Ward HYATT Catton HYATT Davis NONE Kress HYATT Lee NONE Shewmon NONE Siess (Tent) NONE Wylie HYATT Joint ACNW Workina Group /ACRS Occupational and Environmental Protection Systems Subcommittee, May 27, 1992, 7920 Norfolk Avenue, Bethesda, MD, (Gnugnoli/Igne), 8:30 a.m., Room P-422. The joint working group / subcommittee will continue their review of the following six proposed final regulatory guides related to the implementation of 10 CFR Part 20; (1) RG 8.7, Rev. 1, " Recording and Reporting Occupational Exposure, Forms 4 and 5," (2) RG 8.25, Rev. 1, " Air Sampling in the Work Place," (3) RG 8.N.6 " Planned Special Exposures," (4) RG 10.8, Appendix X, " Application of Revised Part 20 to Medical Licensees," (5) RG 8.N.5, " Criteria for Monitoring and Methods for Summation of Internal and External Occupational Doses," and (6) RG 8.N.7, " Radiation Dose to the Embryo / Fetus." Lodging will be announced later. Attendance by the following is anticipated: Moeller Kathren Wilkins Shapiro Underhill Carter [43rd ACNW Meetina, May 28-29,

1992, Bethesda, MD, Room P-110.]

Thermal Hydraulic Phenomena, June 2, 1992, 7920 Norfolk Avenue, Bethesda, MD (Boehnert), 8:30 a.m., Room P-110. The Subcommittee will continue its review of tne General Electric Company's proposed test program to support certification of the Simplified Boiling Water Reactor (SBWR) design and the associated NRC staff's evaluation. Portions of the meeting will be closed to discuss proprietary information applicable to this matter. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of June 1: Catton HYATT Wilkins HOLIDAY INN Carroll HOLIDAY INN Dhir NONE Kerr (tent) NONE Schrock NONE Michelson HYATT Sullivan NONE Ward HYATT Zuber NONE

l 4 i l 3 Ad Hoc Subcommittee on Desian Acceptance Criteria (DAC), June 3, 1992, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m. 12:00 Noon, Room P-110. The Ad Hoc Subcommittee will continue its discussion regarding the use of DAC in the regulatory process and other related matters. Lodging will be announced later. Atten-dance by the following is anticipated: Carroll Shewmon l Catton Ward i Kerr Wylie Michelson i Planninc and Procedures, June 3,

1992, 7920 Norfolk Avenue, Bethesda, MD (Fraley), 1:00 p.m.

4:00 p.m., Room P-422. The i Subcommittee will discuss proposed ACRS activities and related matters. Qualifications of candidates nominated for appointment to the ACRS will also be discussed. Portions of this meeting will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy. Attendance by the following is anticipated, and reservations have been at the hotels indicated for the night of June 2-Ward HYATT Carroll HOLIDAY INN Shewson NONE l 386th ACRS Meetina, June 4-6, 1992, Bethesda. MD, Room P-110 i Agenda to be announced. Joint Computers in NPP Operations / Reliability and Ouality, June 16, 1992, 7920 Norfolk Avenue, Bethesda. @ (Alderman /Igne), 8:30 a.m., Room P-110. The Subcommittees will review NRC research activities for environmental qualification of digital instrumentation and control systems. Lodging will be announced later. Attendance by the following is anticipated: l Lewis Shewmon (tent) Carroll Ward (tent) l Kerr (tent) Wilkins (tent) l Kress Wylie l Michelson l 1 l l l

I I b 1 J l 4 j Imoroved Licht Water Reactors, June 17, 1992, 7920 Norfolk Avenue, Bethesda. MD (El-Zef tawy), 8 : 3 0 a.m., Room P-110. The Subcommittee l will review Chapter 1 of the Electric Power Research Institute's (EPRI's) Requirements Document (Vol. II.and III) for evolutionary and passive plant designs. Lodging will be announced later. i Attendance by the following is anticipated. Wylie Miuelson i Carroll Ward Kress l I Imoroved Licht Water Reactors, June 18, 1992, 7920 Norfolk Avenue, { Bethesda, MD (El-Zef tawy), 8 : 30 a.m., Room P-110. The Subcommittee l will review the Final Safety Evaluation Report (FSER) of the EPRI's Requirements Document for evolutionary plant designs. Lodging will be announced later. Attendance by the following is anticipated: Wylie Michelson I carroll Ward .j Kress t l I Thermal Hydraulic Phenomena, June 23-24, 1992, 7920 Norfolk Avenue, Bethesda, MD (Boehnert), 8:30 a.m., Room P-110. The Subcommittee a will discuss the Westinghouse Electric Corporation's and the'NRC i staff's proposed test programs for support of the AP600 passive plant design certification effort. Portions of this meeting may l be closed to discuss Proprietary Information applicable to this matter. Lodging will be announced later. Attendance by ~ the i following is anticipated: Catton Dhir f Kerr Schrock i Kress Sullivan Ward (tent) Zuber [44th ACNW Meetina, June 25-26, 1992, Hanford, WA.] Auxiliary and Secondary Systems, July 8, 1992, 7920 Norfolk Avenue, l ~Bethesda, MD (Alderman), 8:30 a.m. - 12:00 NOON, Room P-110. The Subcommittee will discuss the ' resolution of Generic Issue 106, ( " Piping and Use of Highly Combustible Gases in Vital Areas." i Lodging will be announced later. Attendance by the following is '] anticipated: i Michelson Catton Carroll Shewmon j Wylie i ) i I

O 5 Plannina and Procedures, July 8,

1992, 7920 Norfolk Avenue, Bethesda, MD (Fraley), 1:00 p.m.

- 4:00 p.m., Room P-4 22. The Subcommittee will discuss proposed ACRS activities and related matters. Qualifications of candidates nominated for appointment to the ACRS will also be discussed. Portions of this meeting will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy. Lodging will be announced later. Attendance by the following is anticipated: Ward ~ Carroll Shewmon 387th ACRS Meetina, July 9-11, 1992, Bethesda, MD, Room P-110 - Agenda to be announced. Ad Hoc Subcommittee on Seoarate and Indeoendent Recuirementa, July 28, 1992, 7920 Norfolk Avenue, Bethesda, MD (Alderman), 8:30 a.m., Room P-110. The Ad Hoc Subcommittee will discuss Key Technical Issue 3, Separation and Independence requirements for Safety Trains. Lodging will be announced later. Attendance by the l following is anticipated: Michelson Kress Catton Wylie ) Imoroved Licht Water Reactors, July 29, 1992 (tentative), 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcommittee will review the Draft Safety Evaluation Report (DSER) of the EPRI's Requirements Document for the passive plant designs. Lodging will be announced later. Attendance by the following is anticipated: Wylie Kress Carroll Michelson Catton Ward [45th ACNW Meetina, July 30-31, 1992, Bethesda, MD, Room P-110.]

1 6 Joint Decay Heat Removal Systems / Advanced Boilina Water Reactors, August 5, 1992, 7920 Norfolk Avenue, Bethesda, MD (Boehnert/El-Zeftawy), 8:30 a.m., Room P-110. The Subcommittees will discuss inspections, tests, analysis, and acceptance criteria (ITAACs) for i selected systems related to GE ABWR. Lodging will be announced later. Attendance by the following is anticipated: Ward Kress Michelson Shewmon Carroll Wylie Catton Davis Kerr l Plannino and Procedures, August 5,

1992, 7920 Norfolk Avenue, Bethesda. MD (Fraley), 3:00 p.m.

- 5:30 p.m., Room P-422. The Subcommittee will discuss proposed ACRS activities and related matters. Qualifications of candidates nominated for appointment to the ACRS will also be discussed. Portions of this meeting will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy. Lodging will be announced later. Attendance by the following is anticipated: Ward Carroll Shewmon 388th ACRS Meetina, August 6-8, 1992, Bethesda. MD, Room P-110 - Agenda to be announced. i [46th ACNW Meetino, August 13-14, 1992, DEFERRED TO SEPTEMBER 24-25, 1992.] i Ad Hoc Subcommittee on Separate and Independent Recuirements, August 19, 1992, 7920 Norfolk Avenue, Bethesda, MD (Alderman), 8:30 a.m., Room P-110. The Ad Hoc Subcommittee will continue the discussion of Key Technical Issue 3, Separation and Independence requirements for Safety Trains. Lodging will be announced later. Attendance by the following is anticipated: Michelson Wilkins Catton Wylie Kress e i

l 7 ComDuters in Nuclear Power Plant Operations, August 20-21, 1992, 7920 Norfolk Avenue, Bethesda. MD (Alderman), 8:30 a.m. Room P-110. The Subcommittee will continue its review of hardware and sof tware issues for digital I&C systems. National experts will discuss software design concepts including safety, reliability, fault-1 tolerance, formal

methods, and verification and validation.

Lodging will be announced later. Attendance by the following is anticipated: Lewis Kress carroll Michelson Catton (tent) Wilkins Kerr Wylie 389th ACRS Meetino, September 10-12, 1992, Bethesda, MD, Room P-110 - Agenda to be announced. Computers in Nuclear Power Plant Operations, September 22, 1992, i 7920 Norfolk Avenue, Bethesda, MD (Alderman?), 8:30 a.m. Room P-110. The Subcommittee will host a special international meeting to hear directly from manufacturers in Germany, France, Japan, 4 U.K., Sweden, and Canada about advanced developments in digital I&C systems. Lodging will be announced later. Attendance by the following is anticipated: r Lewis Michelson Carroll Ward Catton Wilkins Kress Wylie Advanced Boilina Water Reactors, September 23, 1992, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m. Room P-422. The Subcommittee will review the Final Safety Evaluation Report (FSER) i for the GE ABWR design. Lodging will be announced later. Attendance by the following is anticipated: Michelson Shewmon Carroll Ward Catton Wylie Kress Costner [ACNW Workinc Group on Performance Assessment, September 23, 1992 (tentative), Bethesda, MD, Room P-110.) [46th ACNW Meetino, September 24-25, 1992, Bethesda, MD, Room P-110.]

{ o t 8 390th ACRS Meetina, October 8-10, 1992, Bethesda, MD, Room P-110 - Agenda to be announced. Advanced Boilina Water Reactors, October 21, 1992, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m. Room P-422. The Subcommittee will continue its review of the Final Safety Evalua-tion Report (FSER) for the GE ABWR design. Lodging will be announced later. Attendance by the following is anticipated: Michelson Shewmon Carroll Ward Catton Wylie Kress Costner [ACNW Workina Group on Inadvertent Human Intrusion Related to the Presence of Natural Resources at a Hich-Level Waste Site, October 21, 1992, Bethesda. MD, Room P-110.) [47th ACNW lleetina, October 22-23, 1992, Las Veaas. NV.] 391st ACRS Meetina, November 5-7, 1992, Bethesda, MD, Room P-110 - Agenda to be announced. i [ACNW Workina Group on the Impact of Lona-Ranae Climate Chance in the Area of the Southern Basin and Rance, ' November 18, 1992 (tentative), Bethesda, MD, Room P-110.] 392nd ACRS Meetina, December 10-12, 1992, Bethesda, MD, Room P-110 - Agenda to be announced. Advanced Pressurized Water

Reactors, Date to be determined (June / July), Bethesda, MD (Igne).

The Subcommittee will continue its review of the ABB CE System 80+ Design Certification. Topics being proposed for discussion include: Engineered Safety Feature Systems; and incorporation of the requirements resulting from the resolution of USIs and GSIs into the System 80+ design. Attendance by the following is anticipated: Carroll Michelson Catton Shewmon Kerr Ward Kress Wylie

\\ e l l 9 I Decay Heat Removal Systems, Date to be determined (June / July, tentative), Bethesda, MD (Boehnert). The Subcommittee will review the proposed final resolution of Generic Safety Issue 23, "Re. actor l Coolant Pump Seal Failures." Attendance by the following is i anticipated: Ward Michelson Catton Wylie Kerr Davis l Joint Thermal Hydraulic Phenomena / Core Performance: Date to be i I determined (July / August), Bethesda, MD (Boehnert). The Subcommit-tees will continue the review of the issues pertaining to BWR core power stability. Attendance by the following is anticipated: Catton Dhir Wilkins Lee Kerr Lipinski Kress Schrock Shewmon Sullivan Zuber Plant Operations, Date to be determined (July / August), Bethesda, MD (Boehnert). The Subcommittee will continue its review of the NRC staff and industry programs to address the issue of risk from low power / shutdown operations at U.S. nuclear power plants. Attendance by the following is anticipated: Carroll Michelson Catton Wylie Kress Davis Lewis Thermal Hydraulic Phenomena, Date to be determined (early-1993), i Bethesda, MD (Boehnert). The Subcommittee will continue its review I of the NRC staff program to address the issue of interfacing systems LOCAs. Attendance by the following is anticipated: Catton Dhir Kerr Schrock Kress Sullivan Ward Zuber Wilkins l i

't e 10 Thernal Hydraulic Phenomena, Date to be determined, Bethesda. MD (Boehnert). The Subcommittee will review the status of the application of the Code Scaling, Applicability, and Uncertainty (CSAU) Evaluation Methodology to a small-break LOCA calculation for a B&W plant. Attendance by the following is anticipated: Catton Dhir Kerr Schrock Kress Sullivan Ward Zuber Wilkins 1 4 i I 1 l 1

4 APPENDIX IV MINUTES OF THE 385TH ACRS MEETING MAY 6-9, 1992 LIST OF DOCUMENTS PROVIDED TO THE COMMITTEl [ NOTE: Some of the materials listed may have been provided for j ACRS Internal Use Only.) MEETING NOTEBOOE POLICY ISSUES FOR CERTIFICATION OF EVOLUTIONARY AND PASSIVE NUCLEAR i POWER PLANT DESIGNS e Tentative Schedule Status Report with Attachments-o SECY-90-106, dated January 13, 1990 Draft Son of 90-016 (2/7/92) ACRS Report dated April 26, 1990 to Chairman Carr,

Subject:

Evolutionary Light Water Reactor Certification Issues and Their Relationship to Current Regulatory Requirements Staff Requirements Memorandum dated June 26, 1990, from S. Chilk, Secretary, for J. Taylor, Executive Director for Operations,

Subject:

SECY-90 Evolutionary Light Water Reactor (LWR) Certification Issues and Their Relationships to Current Regulatory Requirements Comments of some ACRS members on list of some SECY-90-016 issues Presentation materials provided during the meeting e CONTAINMENT PERFORMANCE CRITERIA TO ACCOMMODATE SEVERE ACCIDENTS Tentative Agenda e Status Report with Attachments: e Memorandum dated April 3,1992, from W. Minners, RES, for R. Fraley, ACRS,

Subject:

ACRS Review of Advance Notice of Proposed Rulemaking (ANPR) on Severe Accident Performance Criteria for Future LWRs with enclosures (Draft) ACRS Report dated January 15, 1992 for Chairman Selin,

Subject:

Proposed 10 CFR Part 50 and Part 100 (Non-seismic) Rule Changes & Proposed Update of Source Term SECY-92-070 dated February 28, 1992,

Subject:

Staff Comparison of ACRS-Proposed Criteria to Accommodate Severe Accidents in Advanced Light Water Reactor Containment Designs with Related Criteria Proposed by Industry (M910607A) Presentation materials provided during the meeting e THERMAL HYDRAULIC PHENOMENA SUBCOMMITTEE CHAIRMAN'S REPORT: GE TEST PROGRAM IN SUPPORT OF SBWR PASSIVE PLANT DESIGN Status Report with

Enclosure:

e Memorandum dated February 26, 1992 from J. Taylor, EDO, for NRC Commissioners, enclosing Advance copy of Draft Commission Paper,

Subject:

Evaluation of General Elec-tric Company's (GE's) Test Program to Support Design Certification for the Simplified Boiling Water Reactor Presentation materials provided during the meeting e

4 e 385th ACRS Meeting Minutes, Appendix IV IV-2 PROPOSED PLAN FOR IMPLEMENTATION OF THE NRC OUANTITATIVE SAFETY GOAL POLICY Tentative Agenda e Status Report with attachments: e SECY-91-270, dated August 27, 1991,

Subject:

Interim Guidance on Staff Implementation of the Commission's Safety Goal Policy Staf f Requirements Memorandum dated June 15, 19 9 0 from S. t Chilk, Secretary for J. Taylor, EDO,

Subject:

SECY 102 - Implementation of the Safety Goals ACRS Report dated September 11, 1990, for Chairman Carr,

Subject:

Implementation of the Safety Goal Policy ACRS Report dated December 18, 1991, for Chairman Selin,

Subject:

SECY-91-270, " Interim Guidance on Staff Implementation of the Commission's Safety Goal Policy" i Staff Requirements Memorandum dated February 21, 1992 [ from S. J. Chilk, Secretary, for J. Taylor, EDO, W.

Parler, OGC, and D.

Ward, ACRS,

Subject:

Staff Requirements - Briefing on Status of Implementation of l Safety Goal Policy Statement (SECY-91-270), 10:00 A.M., 1

Friday, January 17,

1992, One White Flint

North, Rockville, MD Comments of ACRS members T. Kress, H. Lewis, and D. Ward on this subject PROPOSED FORMULATION OF A LARGE RELEASE MAGNITUDE FOR USE IN SAFETY GOALS Tentative Agenda e

Status Report with Attachments: e Memorandum dated April 3, 1992 from W. Minners, RES, for R.

Fraley, ACRS,

Subject:

ACRS Review of Draft Commission Paper on Formulation of a Large Release Magnitude for Use in Support of Safety Goal Policy (encloses Draft SECY Paper) l e ACRS Report dated May 13, 1987 for Chairman Zech,

Subject:

{ l ACRS Comments on an Implementation Plan for the Safety Goal l Policy ACRS Report dated April 12, 1988 for Chairman Zech,

Subject:

e Program to Implement the Safety Goal Policy - ACRS Comments e ACRS Report dated February 16,

1989, for Chairman Zech,

Subject:

Further ACRS Comments on Implementation of the Safety Goal Policy SECY-90-405 dated December 14, 1990,

Subject:

Formulation of e a Large Release Definition and Supporting Rationale Staff Requirements Memorandum dated March 18, 1991, from S. e Chilk, Secretary, for J. Taylor, EDO,

Subject:

SECY-90-405 - Formulation of a Large Release Definition and Supporting Rationale Presentation materials provided during the meeting e

A N 4 385th ACRS Meeting Minutes, Appendix IV IV-3 NRC STANDARD REVIEW PLAN UPDATE AND DEVELOPMENT PROGRAM e Tentative Schedule Status Report e Presentation materials provided during the meeting e IMPLEMENTATION OF THE NRC MAINTENANCE RULE o Tentative Schedule Status Report e e Draft of Report NUMARC 93-01, Revision 1, March 30,

1992,

" Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants" Memorandum dated March 24, 1992, from Robert Baer, RES, for e Gary Zech, NRR,

Subject:

Transmittal of Unapproved Draft of Regulatory Guide to Implement the Maintenance Rule (10 CFR 50.65) Presentation materials provided during the meeting e l HANDOUTS l l e LIST OF FUTURE ACRS SUBCOMMITTEE MEETINGS REPORT OF THE ACRS JOINT SUBCOMMITTEES ON PRA/CONTPOL AND ELECTRICAL POWER SYSTEMS MEETING OF APRIL 22, 1992 e Tentative Schedule l Status Report with Attachments: e ACRS Report dated December 20, 1991 for Chairman Selin,

Subject:

Resolution of Generic Safety Issue B-56, " Diesel Generator Reliability" Certified Minutes of November 20, 1991 Meeting of the AC/DC Power Systems Reliability Subcommittee, November 20, 1991 - Bethesda, Maryland j ACRS member H. Lewis comments on Diesels 1 Letter dated March 5,1992, from Alex Marion, NUMARC, for ACRS Member H. W. Lewis enclosing industrywide data on emergency diesel generator performance Memorandum dated March 30, 1992, from P. Boehnert, for W. Minners, RES,

Subject:

Transmittal of ACRS Member H. Lewis' Personal Comments on Reliability of Diesel Generators (Comments dated March 23, 1992) Memorandum dated March 30, 1992 from M. Steindler, Member Advisory Committee on Nuclear Waste, NRC, for R. Fraley, forwarding information on Diesel Generator Reliability Indicator Annual Diesel Generator Reliability Data Report for 1991 (for each of five DGs at Farley Nuclear Plant) Draf t Regulatory Guide DG-1021 (Second Proposed Revision 3 to Regulatory Guide 1.9, previously issued as Task RS i 802-5) Working Copy of High/ lights / Minutes of the ACRS Joint Subcommittees on Risk Assessment and Electrical Power Systems Meeting, April 22, 1992, Bethesda, Maryland

i 385th ACRS Meeting Minutes, Appendix IV IV-4 RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS Letter dated April 24, 1992 from J. Taylor, EDO, to D.

Ward, e

ACRS Chairman, enclosing written comments to ACRS letter dated March 11, 1992, to J. Taylor, EDO,

Subject:

Proposed Priority Rankings of Generic Issues: Seventh Group Letter dated April 24, 1992, from J. Taylor, EDO, to D. Ward, e ACRS Chairman, in response to ACRS letter dated April 6,

1992, i

Subject:

Full-Height, Full-Pressure Integral System Testing for the Westinghouse AP600 Passive Plant Design SUBCOMMITTEE ACTIVITIES - IPE/5 EVERE ACCIDENTS SUBCOMMITTEE MEETING APRIL 21, 1992 Tentative Agenda e e ACRS Consultant P. R. Davis' Comments on 4/21/92 meeting l e Comments of W.

Kerr, Chairman of IPE/ Severe Accidents Subcommittees regarding April 21, 1992 meeting

" Severe Accident Management Status of Industry Program" e by David J. Modeen, Nuclear Management and Resources Council SECY-92-151, dated April 24, 1992,

Subject:

Issuance of the e Staff's Evaluation Report on the Seabrook Individual Plant Examination Submittal Draf t Minutes of April 21, 1992 Joing Meeting of Subcommittees e on Individual Plant Examinations and Severe Accidents Presentation materials provided during April 21, 1992 meeting e Working Copy of Summary / Minutes of the Meeting of the Thermal e Hydraulic Phenomena Subcommittee on April 23, 1992, Bethesda, l Md. Memorandum dated May 8, 1992 from Gary Quittschreiber, ACRS

staff, for J.

Wilkins, Chairman of Ad Hoc Group for Multilateral International Meeting et al.,

Subject:

May 26, 1992 Preplanning Meeting with RSK Members i Memorandum dated April 6, 1992 from R. Savio, ACRS, for ACRS e Members,

Subject:

Future ACRS Activities - 386th ACRS Meeting June 4-6, 1992 with attachments !}}