ML19224D281
| ML19224D281 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/31/1979 |
| From: | Mattson R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907110258 | |
| Download: ML19224D281 (9) | |
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D 3 I 1979 Note to: Distribution From:
Roger J. Mattson 2
Subject:
MEETING MINUTES FOR L ON TMI-2 D. Ross and his task force gave status on bulletin responses from B&W, CE and W.
B&W responses were reasonable; CE were not quite as good. W customers did not pass on to us what W gave to them. Many responses were inadequate or incomplete or incorrectT Ross plans to deal with W and ultimately all the utilities through owners groups. There will be a meeting tomorrow in P-110/ll4 with E and 19 of its owners.
W and CE are being required to respor1 to the Michalson report in the same manner as B&W.
E will be told to simulate reactor behavior for various small breaks.
In interim, NUREG-0560 has been sent to all plunts.
The Division of Technical Information and Document Control is issuing a chronological list of all TMI documents to date. W. Minners is working on a master index.
New requirements flowing from TMI-2 need to be summarized in one place - Conran's list of completed actions will do this, eventually.
At least one of D. Ross' people will attend each L2 meeting (Heltemes designated,).
There was a meeting with the Commission on 5/19 discussing the feedback of '
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operating experience of auxiliary systems and what to do with LERs. A Commission paper should be going down with recommendations and actions taken sometime this week.
The Commission will probably act on it within the next two weeks.
D. Davis'(DOR) was Director of task force. He summarized the conclusions of the study and left a copy of the task force report for distribution td~the.L ask force.
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R. Mattson passed out two-page summary of L2 function and a subject category '.ist c; 12 areas of function description (enclosed). He asked that L2 members:
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look at category list identified and enlarge descriptions to cover scope of things you think should be included.
2.
take their individual list and characterize it by some broad headings.
Make them fit under the 12 categories.
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After receipt of completed material, Minners will prepare a memo from Mattson to Denton giving him the status of what the task force is doing with copies to IE, flRR managers, RES, and 3D.
By Wednesday, COB, May 30, 1979, L2 staff is to provide an annotated version of subject categories to W. Minners.
B. Cudlin will be assigned ill - Policy.
It will take two to three weeks trying to get everything catalogued.
H. Silver is to complete the description of new OL licensing requirements by 6/15/79, based on input from L2 members.
ACRS wants quantitative reactor safety criteria (r.u.d r duem. % M d b b m k \\ w Jb.
fleed for changes in tiRR emergency preparedness program to be coordinated with L2 task force (concurrence). Mattson will get additional person from DSE to work on L2 task force. He would serve as contact for work done on emergency preparedness requirements.
Holman will research who are tae proper policy people at FAA for discussions 2
with L, e.g., M. Carbon counterpart of NTSB and H. Denton counterpart of FAA.
Concerning auxiliary feedwater systems, Ross' people may be doing everything needed in this area; C. Long will coordinate. Mat Taylor will be asked to come to our meeting on Monday, June 4 to discuss auxiliary feedwater studies and general fault tree studies of TMI-2.
R. Tedesco was assigned to contact Taylor.
H. Silver, T. Telford, aad L. Chandler are only'3 people working on L2 less than, full-time, but as of 6/1/79, Telfo.rd and Silver wilI be full-time.
By Monday's L2 meeting, will know whether we have secured P-500 exclusively for the task force.
A summer intern will be in to help with catalogue updates.
J. Cenran has responsibility for keeping an up-to-date list of completed actions post-TMI-2.
Summary descriptions of work in progress should be kept in catalogue and updated every two weeks - decision later on formalities.
If you have any suggestions for thanging form, contact W. Minners as soon as possible.
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Roger J. Mattson Enclos ures :
As stated
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2 TASK FORCE ON TMI-2 CALENDAR OF M_EETINGS SCHEDULED RELATED TO L 7 ~~ 'e esday, May 30, 1979 Meeting with AIF Steering Committee on TMI-2 Pennsylvania Ave. (lith Fl.') Byron Lee is contact R. Mattson will attend. Meeting with Westinghouse at 9:00 a.m. P-110/ll4 2 C. Long and H. Silver to attend from L Thursday, May 31, 1979 Meeting with ACRS Subcommittee on TMI-2 Accident Implications at 8:30 a.m. May 31 - June 1,1979 Room 1046 - H Street Mattson and Conran to attend. 2 Meeting of L TMI-2 Task Force at 8:30 a.m. with OLB and QAB P-422 Friday, June 1, 1979 Testimony at Presidential Committee on TMI-2-at 9:00 a.m. ~ ~ ~ New Executive Office Building, Room 2008 Roger J. Mattson and Robert Tedesco will attend. Wednesday, June 6 and Thursday, June 7, 19'/s Meeting with TMI-2 ACRS Subcommittee at Harrisburg (TMI Site) at 1:30 p.m. aJL
Lesson Learned ~ ~ ~ This Task for the TMI-2 accident includes the review and evaluation of. investigative information, staff evaluations of responses to I&E Bulletins and orders, staff recommendations and recommended actions from outside of the NRC; to identify, analyze and recommend changes to licensing requirements and the licensing process for nuclear power plants based on the lessons learned and provide recuamendations for interim requirequirements for new operating licenses prior to completion of long-term activities. There is a range of area of immediate interest to NRR in which possible regulatory improvements are suggested by the TMI accident. These include: (1) Reactor operator training and licensing. (2) Reactor transient and accident analysis. (3) Licensing requirements for safety and process equipment, instrumentation, and controls. (4) Offsite and onsite energency preparations and procedures. (5) Reactor siting. (6) Licensee technical qualification. ~4 L 1 O s.) t.'r
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(7) NRR accident response role, capability and management. (8) Reactor operating experience (9) Environmental Effects (10) Licensing requirements for post-accident monitoring and controls. (11) Post-Accident Cleanup and Recovery. ~ (12) NRR engineering evaluation of the. TMI-2 event sequence. End-products may take the form of proposals for changes in legislation, policy, regulations, staff technical positions, review procedures, or NRR organizational st.ucture and respcnsibilities. All information developed by the Task Force will be made public and submitted to others investigating the TMI-2 accident. The Task Force will serve as the focal point for NRR interaction with these groups. ,9 n 3OL 't(
Subject Category 1. Reactor Operations' 1.1 Plant Procedures - Tel ford /IE 1.1. i Technical Spegifications 1.1. 2 Emergency Procedures 1.2 Operator Training and Licensing - Milhoan/Hulman 1.2.1 Operator f';alification ' 2.2 Operator Examinations 1.3 Conduct of Operations 1.3.1 Licensee Technical Quali"ications 1.3.2 Health Physics 1.3.3 Staffing ~1.3.4 Maintenance 1.4 Man / Machine - Beltracchi 1.4.1 Control Room Design 1.4.2 Computer Aids 1.4.3 Diagnostic Instruments 2. Transient ahd Accident Analysis [ 2.1 System Analysis - Holahan/Cudlin 2.1.1 Accident Analysis 2.1.1.1 Loss of Coolant 2.1.1.2 Low Probability Accidents 2.1.1.3 Core Cooling Operations 2.2 Radiological Consequence Analysis - Stoddard 2.3 Analysis Methods - Hol.han/Cudlin 2.3.1 Code development 2.3.2 Code verification 2.3.3 Research 2.3.4 Licensing requirements ,7 0 / 3 J G. ("'
2 3. Licensing Requirem'ents for Safety and-Process Equipment, Instrumentation And Controls ~ 3.1 RCS - Olshinski/Voglewede 3.1.1 Overpressure Protection 3.1.2 Steam Generator "~ 3.1. 3 Reactor Coolant Pump 3.1.4 Pressurizer 3.1. 5 Venting 3.2 Radiation Protection and Control - Stoddard/Barrett 3.2.1 General 3.2.2 Plant design and shielding 3.2.3 Ventilation system 3.2.4 Radwaste system 3.2.5 Radiation Monitoring 3.3 ESF 3.3.1 AFW/FW - Long 3.3.2..ECCS - Olshinski/Voglewede ~ 3.3.3 Containment - Milstead 3.3.3.1 Isolation 3.3.3.2 Hydrogen Control 3.3.4 RHR Systea Olshinski/Voglewede 3.3.5 Auxiliary Systems - Long 3.5 Instrumentation and Control - Calvo
- 3. 5.1 Plant I&C 3.5.2 Protection System 3.5.3 ESF I&C 3.5.4 Instruments to Follow the Course of an Accident - Calvo/01shinski/Stoddar:
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3 1,6 Electrical Power - Calvo 3.7 Design Requirements 3.7.1 Environmental -Qualification - Milstead 3.7.2 Quality Assurance 3.8 Pre-Operational Testing 4. NRR Requirements for Offsite and Onsite Emergency Preparations and Proceddres - ? 4.1 General 4.2 Licensee 4.3 Local 4.4 State 4.5 Federal t 6. Sdc ard-'/ 5. NRC Accident Response Role, Capability and Management - ?/IE 5.1 Emergency Communications 5.2 Radiation Monitoring 5.3 Analysis Support 6. Reactor Operating Experience - Telford 7. Envir~onmental Effect - Stoddard 8. Licensing Requirements for Post-Accident Monitoring - Calvo/01shinski/Long and Control 9. Post-Accident Cleanup and Recovery - Stoddard
- 10. Investigation and Evaluation of the TMI-2 Accident - Minners SOttc/b11
- 11. Policy 11.1 Standardization 11.2 Risk Assessment / Safety Goals 11.3 Reactor Siting 11.4 Audit Review 11.5 NRC Role in Accidents b b 2 [)'-)
4 ~ r p ~. ~f 12.1 Pending CP and OL Actions - Sjlyer 12.2 ACRS Coordination 12.3 Industry Coordination - Conran 12.4 Varga Coordination 12.5 Congress Coordination 12.6 Document Control - Ireland 12.6.1 Green Tickets 12.6.2 Catalogue e= w* y e e b d b
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NRR Lessons Learned Task Force ^' ' Room No. Office No. Home No. R. Mattson, DSS P-1102A 27517 340-7864 R. Tedesco, RS P-ll22B 23090 424-5991 W. Minners, DSS P-1106 27581' 469-7449 R. Ireland, RS P-1122A 28084 926-8576 C. Long, PS P-822 27754 253-3359 T. Tel ford, D0R 530 28102 469-6341 J. Olshinski, RSB P-ll32E 27591 (70?' 938-3092 J. Calvo, PSB P-832 27276 340-8775 J. Voglewede, CPB P-1112 27603 460-3047 W. Milstead, CSC P-904E 27711 473-8717 (L. D.) H. Silver, DPM 120 27831 647-8559 (L. D.) J. Conran, DPM 243 27745 340-2355 P. Stoddart, ETS3 P-700A 27775 924-4305 H. Krug, RAB ~ P-700C 27955-468-9037 G. Holahan, AB P-1030A 27588 593-5960 L. Beltracchi, ICSB P-720C 2)233 340-3138 J. Holman, OLB 362 27487 840-0274 L. Chandler, ELD MNBB 10217 28658 983-1908 J. Milhoan, SD P-1196 27581 924-2691 B. Cudlin, RES 529 27980 530-0281 S. Bryan, IE* Not a member 28019 926-1065 IE contact until permanent member named ,~ m-q ))q / i_ JU -}}