ML20213E211
| ML20213E211 | |
| Person / Time | |
|---|---|
| Issue date: | 06/10/1982 |
| From: | Ross D NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Bassett O, Bernero R, Minogue R NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20213E209 | List:
|
| References | |
| FOIA-87-113, FOIA-87-60 NUDOCS 8207280120 | |
| Download: ML20213E211 (7) | |
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/gme%qA NUCLEAR REGULATORY COMMISslON UNITED STATES 2
WASHINGTON, D. C. 20885 r.
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=-l June 10, 1982 MEMMANDLM F(R: Those on Attached List
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FRCM:
D. F. Ross, Deputy Director Office of Nuclear Regulatory Research
SUBJECT:
SEVERE ACCIDENT RESEARCH PROGRAM (SARP)
This letter is directed to the NRC staff and research contractors who are 3
working on the Severe Accident Research Program (SARP). The intention is to provide general guidance on the conduct of the SARP and specific i
information on forthcoming interactions with the industry degraded core study group (IDCOR).
For many years the NRC has regulated nuclear reactors using a safety review process which relies on a careful analysis of a plant's ability to endure a spe.ctrum of design basis accidents. The Three Mile Island accident reminded i
us that severe core-damaging accidents, beyond the design basis can occur.
The SARP ms set up to analyze severe accidents in light water reactors in order to obtain a better understanding of their likelihood and their consequences, and to determine what changes in design or operation could i
be worthwhile in reducing the risk of severe accidents. Our first priority is to deal with these questions for operating reactors, and for reactors in the review process.
In SARP we are gathering technical information. The IDCOR group is also gathering information on the same subjects.
In order to enhance the effectiveness of our research program we have arranged for a series
- of technical exchange meetings on SARP topics. These meetings will be limited in number to ensure that the time given to information exchange does not adversely affect other work. The meetings will be between the technical personnel working on these topics. Technical information will be exchanged; regulatory or licensee policy will not be discussed.
I understand that EPRI will participate where it has worked on a topic. The ta:hnical meetings will be open to public observation, but not participation.
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- Additional meetings will be determined and scheduled at the September 1982 mana.gement meeting..
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Thosed on Attached List -
The attached table lists the meeting agenda which was agreed to in an.
NRC-IDCOR meeting on May ll,1982. For each technical meeting a detailed technical agenda will be drawi up about one month prior to the meeting. The contacts listed for the meetings are responsible for preparing the agenda and for documenting technical differences ideatified in the meeting.
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~m D. F. Ross, Deputy Director Office of Nuclear Regulatory Research Attactment:
NRC-IDCOR Interface Meetings 4
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6 NRC-IDCOR INTERFACE MEETINGS TOPIC DATE PLACE CONTACTS Severe Fuel Damage June 11,1982 Washington, DC Ian Wall, EPRI John Larkins, NRC Terry Tyler, TEC Risk Codes and Value-July 7, 8, 9, 1982 Albuquerque,IM Mark Cunningham, NRC Impact Methodology Terry Tyler, TEC Accident Sequences late, August 23 or Knoxville, TN Pat Baranowsky, NRC (ASEP,SASA,IREP) 24, 1982 John Larkins, NRC Terry Tyler, TEC Management Interface September 24,1"-
Chicago, IL Denny Ross, NRC Anthony Buhl, TEC Ian Wall, EPRI Accident Source Terms October 1982 Washington, DC John Larkins, NRC Terry Tyler, TEC G
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F Addressees - Memorandum Dated June 10, 1982 '
NRC/RES INEL
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R. B. Minogue L. J. Ybarrondo R. M. Bernero H. J. Zalie
- 0. E. Bassett M. Stewart C. N. Kelber W. Sullivan f
G. R. Burdick T. Howe G. K. Tomlin J. Hunter P. W. Baranowsky R. M. Blond ORNL-J. A. Murphy M. A. Cunningham /
T. Kress M. Jankowski S. Hodge M. Silberberg R. Wichner G. P. Marino R. R. Sherry BCL R. W. Wright R. T. Curtis R. Denning J. T. Larkins J. Gieseke NRC/NRR LANL H. Denton N. Demuth E. Case R. Mattson PNL S. Hanauer C. Hann SNL W. Lustcotoff A. W. Snyder D. McCloskey J. Walker J. Hickman G. Varnado D. Aldrich A. Benjamin A. Kolaczkowski J. Rivard E. Haskin D. Powers M. Berman M. Clauser R. Cole e
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NRC-IDCOR AGREEMENTS AND SUBSEQUENT ACTIONS
- rkins, as aided by Cunningham, Costello and Norberg are responsible 1.
.a agents for the redraft of NUREG-0900.
2.
Chapter 1 has been redrafted and will be reviewed by Bassett/Bernero.
3 Costs wil! be included only a general sense (down to elements).
4 NUREG-0900 will be transmitted to Commission separate from SECY-82-1A.
5.
The redraf t will have tw'o distinct plateaus (a 2-year result in Jan. '84, and a.1-year resul t in Jan. '86).
The goal is to produce enough information to make SA decision on ors and pipelino plants by 1-84 consistent with subsequent policy expressions of SECY-82-1A.
(The NRC is less confident of meeting this goai on the lower-pressure containments than on large, dry containments).
6 Tne 3900 redraf t is due to DAE, ORA, OET, and 0F0 management by C.0.8.
2 April '82.
It should be to RES office management n.l.t. 7 April.
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giddT is' trfrismit to Dircks by 12 April.
7.
IDCOR EPRI, and RES will meet in the first part of May to discuss program organization, integrated schedules, and subsequent technical meetings.
The nominal date is 10-11 May, in Chicago.
NRC will provide in advance updated flow chart and detailed time lines.
L We greed that one topical specialist meeting (early) will be on Operational Impact of the Severe Fuel Damage part of SARP.
9 NUREG-0900 redraf t will cite, on a best-effort basis, the resul ts of other dark,(e.g., EPRI, foreign, IDCOR).
10 We will consider whether specification of anu survival of minimum equipment dould be part of our SARP-(See IOC09 element 17, for example).
11.
We agreed that an early technical exchange iiteeting is needed on state-of-
'the-art of value-impact analyses and methodology, and theory of tradeoffs of prevention vs. mitigation in tenns of risk reduction, including generic applicability.
This meeting should be in late May, or early June, in Albuquerque.
12.
We agreed that we need a specialist meeting on a.cident management; this would include our SASA program, as 1 minimum.
It would also include IREP/NREP' (including typicality of reference plants).
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- 13. We will consider a peer review process for our work.
14 We al ti consider writing periodic (6 month?) progress reports, by eWent.
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(Refer to item 7).
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2-We agreed that during all specialist meetings it will be appropriate to 15 discuss the necessity for the work, and why the scale selected is appropriate.
We will.try to have an organizational meeting with ACRS SCM in late Miy.
16.
We will schedule a specialist meeting on risk code development and i7.
'iJtilization.
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TABLf 'i 3ROJECTED -.f!TEPFACF MEETIN0 (NRC-iDCOR)
DESCRIPTION TIME
..P..L..A.C..E.-_ -. i _
AG. E._N_D.A.... _.. _
..___ A. T_T_E.N.D.E. E_S_
B.
Management y
Ma y 10-11 Cnicago j
Program organizatiun, Management of NRC, IOCOP, "eeting on v
l integrated schedules, EnPI I
subsequent rechnical 0rganization ano i
Priorities
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meetings I
_.n. w Sandi'a, PNt -8CL 2.
Value-impact C. ', i...
Al buquerque Tradeoffs of prevention vs. mitigation-ongoing N ---
Methodology Tw\\p Sandia study 3.
Opera tional June Idaho Falls Relationship of SFD to INEL, Sandia, PNL Impact of SevereQ; Regulatory, Operational Fuel Damage and Technical Aspects t-
' 2.1.h June TBD Analytical results to Various RFS contractors 4.
- SASA, s-IREP, NREP
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date V
tRD Latest experimental,
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j 5.
S cean.
g Sandia analytical casults Explosion g
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6 Accident Source Sept. '82 TBD i
More realistic source i
oRN!, BCL, Sandia Terms l
term work i
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7 Risk Coaes June-July TRD Comparison of methods BCL. Sandia and development _ plans g I f
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