ML19224C123
| ML19224C123 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/25/1979 |
| From: | Major R Advisory Committee on Reactor Safeguards |
| To: | Okrent D Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML19224C120 | List: |
| References | |
| NUDOCS 7906290049 | |
| Download: ML19224C123 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISCION
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS hnssff o
WASHINGTON, o. C. 20555
% * %.- y May 25, 1979 Dr. D. Ckrent, Chair:r.an Ad Hoc Subw..dttee on the
?aree Mile Island 2 Accident Implications SUBJEC"': CRAPr 2 0F 'IEE 'IMI-2 ACCIDENT IMPLICATICNS FIETmG SCHEDULE -
FAY 31 - JUNE 1,1979 - WASHIlUK;N, IX' Attached is a revised schedule for the abcVe meetirg. 'Ihc new Ochedule reflects a reordering of presentations only, there have been no major additions or deletions in the topics to be discussed. 'Ihe meeting place remains the same: Room 1046 of 1717 H St., NW, Wachington, DC and attendance is still anticipated for the followirq mer.cers and consultants:
M. Carbon I. Cattor H.;Ftherington W. Lipint.i W. Kerr C. Michei.on S. Lawreski T. Theeft cus M. Plesset J. Ray C. Siess O
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f Richard Major Reactor Ergineer Attac.%ent:
As stated ec:
R. Fraley, ICES S. Levine, RES E. Jordan, I&E M. Gaske, ACRS R. Scroggins, FIS H. Wilber, I&E M. Libarkin, ACRS R. Budnitz, PES J. Davis, I&E J. ftKinley, ACRS R. Boyd, D24 W. Oircks, I&E P. Tam, ACRS D. Pess, DR4 R. Minogue, CSD L. Gossick, EEC L. Crocker, CPM R. DeYoung, CSE H. Denton, NRR J. Helte:r.es, DPM E. Case, NRR R. Mattson, DSS D. Eisenhut, NRR R. Tedesco, DSS S. Hanauer, IES
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/CES SUDCCretITTEE CN THREE MILE ISIAPD-2 ACCIDENT IMPLICATICr43 May 31 - June 1,1979 v
8:'
A.M.
DISC"SSICN WITH NRC STAFF Introduction (1) Discussien of Staff proposal for augrmnted research and technica1. assistance (STAFF: NR9, RES, FlX))
(2) Researh on IMI during recovery process.
(update of previous discussions) - (STAFF)
(3) 8 /02 - generation under Accident Conditions (STAFF: NPR & RES) 2 EREAK (4) Preliminary discussion on implications of TMI-2 for a Boilirq Water Research (STAFF)
(5) Generic Report on Feedwate Transients - Other Questions Arising from Specific design considerations for various B&W plants:
Exar:ples:
Seismic qualifications of auxiliary feedwater pipirn and water supply.
- Auxiliary feedwater piping arrargement at Oconee Others 1:00 P. M.
IIINCH 2:00 P. M.
Discussions with B&W Introduction (1) Chronology of Events - hhen was B&W first notified of incident? hhen did s&W start to give technical assistance to Met. Ed.? What assistance during ist 24 f. curs? Other customers? Response team formed?
(2) Response to I&E Bulletins 79-05,79-05A, 79-058.
(3) Proposal for Adequate Interium Cperator "4Taining and Adecuate instrumentation.
256 529 e
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5:00 P. M.
(4) Simulation Capability (5) How is Operatirq Experience processed /used?
(B&W) 7:00 P.M.
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6 JUNE 1, 197.9 8:30 A.M.
(B&W) 1.
Specific studies on T4I-2 2.
Stull areak Studies 3.
Hardsare char >3es 4.
Guidelines for operators 5.
Natural Circulation Coolirn (to include a discussico of transitien phase le. frcra a water solid natural circulation mode to a boility/condensirg mode of natural circulation cooling.)
6.
Ccmbined Transients 8.
Others (Copies of draft or final studies on the above topics w>uld aid the Sabcemittee) 10:30 A.M.
BREAK 9.
(NUREG: 0560. Staff Rep:rt on the Generic Assessment of Feedwater Transients in Pressurized Water Reactors Desi ned by the Babcock and Wilcox Company by !aR).
i 10.
Effects of Icop Seals and OPSG on Reactor Behavior.
11.
Results of Failure Mode and Effects Analysis on I.C.S.
(B&W) 12.
Sumary (High Lights responses to ACDS reports.)
1:00 P.M.
ILNCH 2:00 P.M.
... 0ther Tcpics as Time _Pepits - (S"'AFF)
Frequency of challenges of safety system a.
b.
Single failure criterion c.
Jse of shared facilities d.
Other design features to reduce the probability of accidents (e.g., plant simplification, impreved :sterials, separatien of centrol and safety systems)
Other design features to reduce the consequence of accidents e.
(e.g., improved separation of barriers) 256 330 e
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t June 1, 1979
. f.
Ib standardi::ed plants inhibit safety improvmonts?
g.
List of equi;xnent Miich must operate h.
Use of probabilistic vs. deterministic criteria /
p evaluation (consider multiple htran errors, etc.)
1.
Use of computer assist to operator i
short term - ?
long term monitor status /positon of imrectant components / valves I
- j. Added emphasis on small/very =all breaks.
i.
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Research related to path of molten core release.
l' l.
Cesign all 5ICS systems to take full primary systm pressure so that pressure interlocks are not needed cc valves and operator doesn't need to take so many actions depending on his estimate of the pregress of an accident.
Effectiveness of valve locks (at 'DtI-2 the operators m.
broke the locks)
I h.
Provide more RPR loops i
l" 4:45 P.M.
Discuss Futuro Subcomittc Actions t
j 7:00 P. M.
AIUOURN 256 33i
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