ML20030B907
| ML20030B907 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/14/1981 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20030B908 | List: |
| References | |
| NUDOCS 8108250176 | |
| Download: ML20030B907 (5) | |
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AUGUST 1 4 1981 ed
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AUGUST 4 1981
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Docket No. 50-313
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LICENSEE: Arkansas Power & Light Company (AP&L)
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VS,/A' g-FACILITY: Arkansas Nuclear One, Unit No.1 (ANO-1)
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SUMMARY
OF MEETING OF REPRESENTATIVES FROM THE OFFICE OF
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SUBJECT:
t NUCLEAR REGULATORY RESEARCH AND THEIR CONTRACTORS WITH AP&L!
CONCERNING THE ASSISTANCE OF AP&L AND TNE USE OF ANO-.1 IN THE SEVERE ACCIDENT SEQUEJ4CE ANALYSIS (SASA) PROGRAM Introduction l
The meeting was held in the AND Emergency Response Center near the ANO site at the request of tne NRC staff to discuss the SASA program and the as-The meeting sistance of AP&L in the use of ANO-1 in the SASA program.
The attendees are identified in Enclosure followed an agenda, Enclosure 1.
Visual aids for the presentations of the Idaho National Engineering 2.Laboratory (LANL), and Sandia National Laboratory (SNL) concerning the PWR analysis on the Zion Reactor are included in Enclossres 3, 4 & S, respectively.
Visual aids for the Oak Ridge National Laboratory (ORNL) conceming the BWR analysis on the Browns Ferry Reactor are included in Enclosure C. ~
Visual aids for the SNL discussion on the proposed efforts on ANO-1 are included in Enclosere 7.
Background
The primary objective of the SASA program is to improve the understanding of reactor accident phenomenology and of the human-machine interface during events beyond the desi'gn basis.
Secondary objectives are to evaluate the capability for arresting and mitigating the consequences of severe core damage accidents and to evaluate potential improvements in those capabilities, if warranted. Thess objectives would be met by analyzing the plant response to the most likely accident initiators, using best-estimate rather than The plant response to operator actions would be conservative methods.
analyzed. The impact of training, procedures, and current regulations on
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operator action would be considered.
The SASA prcgram would use the IREP studies to identify the most prc'0able I
accident sequences for the study. SASA techniques have been applied to the Zion and Browns Ferry Reactors.
W..h Zion, a range of small break 1
LOCAs in combination with other failure sequences (similar to sequences analyzed in WASH-1400), which are likely to lead to core uncovery, were The calculations for these reviews assumed realistic or best analyzed.
estimate conditions and assumed operator acticns based on existing training j
procedures - and instrumentati on, l
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SASA 50-313 i The consequences of these sequences were analyzed with or without operator g
actions to assess the effectiveness of mitigating actions during'these severe accident sequences.
With Zion and Browns Ferry, similar analyses and reviews have been done on the_ station blackout event in combination with other failure sequences and as failure of auxiliary feedwater system, stuck open PORY or ruptured e ar.. generator relief valve.
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From these reviews and analyses a catalog of " accident signatures" is being developed.
An " accident signatures" basically identifies an accident j
sequence by the parameters of the RCS and corresponding results associated with different operator actions or inactions.
The catalog of accident I
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signatures would be a reference document which could contribute to training and aiding operators to diagnose and respond to severe accident sequences based on the results of the SASA analysis.
Discussion of Support fleeded From AP&L The SA5A program with Ar10-1 as a model consists of a front end ans'.ysis (before core melt) and a back end analysis (after core melt).
Since these analyses i
would be best estimate analyses, they would need AP&L support to provide detailed plant information such as: pump performance curves, vessel details, containment geometry and structural details, plant equipment details and, ins trumentation details. The support which was specifically requested from AP&L included: (1) One AP&L employee full time for one week to support a site visit for the collection of detailed information, (2) Telephone contact with AP&L through December 1982, (3) AP&L review of SASA reports through f
December 1983. AP&L would be invited but would not be required to attend SASA progres: meetings.
AP&L hcs since considered their participation in thc SASA program and have declired to participate on the basis that they believe a full time man was needed to provide the needed progr'- support and that AP&L could not afford that type of commitment at this tin.c.
i original signed try Guy S. Vissing, Project Manager Operating Reactors Branch #4 l
Division of Licensing Enclo;ures :
1.
Agenda 2
List of Attendees 3.
Vinual Aids used in Presentation 4.
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nac ronu na nomiNacu ano OFFICIAL RECORD COPY usceo m _us. a
_ MEETING
SUMMARY
DISTRIBUTION Licensee:
Arkansas Power & Light Company ~
Copies also'sent to those people on service (cc) list for subject plant (s).
Docket FiTe NRC PDR L PDR-ORB #4 Rdg TNovak JStolz Project Manager - G. Vissing Licensing Assistant - R. Ingram OELD Heltemes, AE0D IE-3 4
SShowe (PWR) or CThayer (BWR), IE Meeting Sunwary File-0RB!4 RFraley, ACRS-10 Program Support Branch J01shinski BGrimes, DEP SSchwartz, DEP SRamos, EPD3 FPagano, EPLB R. Curtis L. J. Callan, RI-ANO W. D. ' Johnson, RI-ANO J. K. Long 4
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nclosure 1 AGENDA Briefing for Management of Arkansas Power and Light Company on NRC's Severe Accident Sequence Analysis (SASA) Program July 30; 1981 ~
Opening Remarks and Introduction G. Vissing, NRC/NRR of Attendees l
Review of Agenda and Background on R. Curtis, NRC/RES NRC SASA Program
'l PWR " Front-End" Analysis and Recommendations on Zion Reactor:
Idaho National Engineering Laboratory (INEL)
J. Hunter Los Alamos National Laboratory (LANL)
N. DeMuth Break l
PWR "Back-End" Analyses and Recommendations on Zion Reactor:
Sandia National Lab' oratory (SNL)
J. Darby BWR " Front and Back-End" Analyses and Recomendations on Browns Ferry Reactor:
Oak Ridge National Laboratory (ORNL)
S. Hodge i
QuestionsandDisctIssionPeriod i
Lunch Pronoced SASA Efforts on ANO, Unit 1 J. Darby Proposed Arrangement with AP&L R. Curtis o Relationship with Commonwealth Edison
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o Administrative Lines o Expectations o Mutual Advantages t
Response by AP&L AP&L Joint Fonnulation of Conclusions Group i
Adjourn
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ATTENDEES JULY 30, 1981 SASA MEETING WITH AP&L NRC AP&L R. T. Curtis L. D. Young L. I i
L. J. Callan, Resident Inspector, AN0 L. J. Dugger W. D. Johnsen, "
D.'Rueter J. K. Long J. M. Griffin G. S. Vissing D. Williams W. T. Craddock J. F. Stolz J. Robertson DOE-Idaho
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P. E. Litteneker J. Marshall SANDIA D. E. Taylor J. Darby MSS T. Temple
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