ML20236P669
| ML20236P669 | |
| Person / Time | |
|---|---|
| Issue date: | 11/10/1987 |
| From: | Wohl M Office of Nuclear Reactor Regulation |
| To: | Butcher E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20236E846 | List: |
| References | |
| NUDOCS 8711180095 | |
| Download: ML20236P669 (3) | |
Text
_.
p ua o
UNITED STATES y
./'
f p,
NUCLEAR REGULATORY COMMISSION 5
- p WASHINGTON, D. C. 20$$5
%......o NOV 101987 MEMORANDUM FOR:
Edward J. Butcher, Chief Technical Specifications Branch Division of Operational Events Assessment, NRR THRU:-
David C. Fischer, Section Chief
~
Special Projects Section
. Technical: Specifications Branch Division.of. Operational Events Assessment,.NRR FROM:
Millard L. Wohl, Reactor Engineer Special Projects 'Section Technical Specifications Branch Division ~ of Operational Events Assessment, NRR
SUBJECT:
SUMMARY
OF MEETING WITH NUMARC/BNL/INEL/SAIC ON TSIP TOPICAL REPORT REVIEWS /PROBABILISTIC METHODOLOGIES The OTSB staff met with personnel from NUMARC.. BNL, INEL ~and SAIC 'on the status l
of TSIP-related topical report reviews and probabilistic methodologies relevant-l to these reviews. The following is a'sunnary of the major issues reviewed:
Non-Extrapolability of Plant-Specific ESFAS' Conclusions l
While INEL felt that surveillance interval (SI) and allowable outage time.
(A0T) extension requests related to the Calvert Cliffs ESFAS were acceptable.-
they had strong reservations about extrapolating this. acceptability'to other CE plants, for which the ESFAS and ESFAS/ fluid ~ system interactive modes are different. BNL had similar reservations about the appropriateness of attempting to extend any conclusions reached on M111 stone-3'ESFAS SI and A0T extensions 'to other W plants. Use of ASEP models might help to
~
resolve these problems.
Need for Conditional Core Damage Frequency Information BNL was concerned that actual conditional core damage. frequencies, when'a system is in test or maintenance, were not being presented in topical reports.
Instead, average unavailabilities were being'used in topicals to attempt to justify AUT extensions; these average unavailabilities are.
inappropriate for this purpose.
Discussion of ASEP Model_s, The ASEP program examined and categorized seven or'eight major plant systems and developed models for a total of fifty to sixty systems.
The ASEP models require validation, and AE00 is planning to soon issue a request to utilities to selectively establish'such validation. The.
ASEP models are presently believed to be conservative, but validation-
/
could reduce core melt frecuency uncertainties by about a factor of five. -
y.1 (
Contact:
M. Wohl x27458
. y B711100095 B71110 t
REVGP: ER9gC -
.)
NOV 101987 Edward J. Butcher '
Performance Indicator Program AE0D is planning to issue a draft Commission Paper on Performance.
Indicators in January,1988. This paper will highlight methods of calculating system unavailability and alternative methods of relevant system data collection for several systems in 108 plants. OTSB will watch this program closely because it relates directly to our proposed TSIP Phase III data oriented technical specification ideas.
PETS Program Numerical Criteria PETS has developed acceptable changes in unavailability (numerical criteria) based on extrapolation of plant-specific operating history.
I These criteria are also linked to the Commission Safety Goal. is an attendance list; Enclosure 2 is the meeting announcement.
Another similar meeting may be held in about two months.
l M
Millard L. Wohl, Reactor Engineer l
Special Projects Section Technical Specifications Branch Division of Operational Events Assessment, NRR
Enclosures:
As stated cc: w/encls.
T. E. Murley R. W. Starostecki C. E. Rossi Distribution OTSB R/F DOEA R/F i
PDR l
'CentralcFiles t CERossi EJButcher DCFischer MWohl OTSB Memebrs CHBerlinger WDLanning JConran DBrinkman SNewberry MChattersou OT,Sp:
R OTSB:NRR MLwdf?
p DFischer 11/of/87
/1/ fv/87
{;:..
~
.;)
ENCLOSURE'l LIST OF ATTENDEES NAt1E AFFILIATI)N, PHONE NO.
Dick Robinson NRC/RES
.(301) 443-7627 3
Marty Sattison INEL/NRC Risk Analysis (208) 526-9626 Carl Obenchain INEL/NRC Tech. Support (208) 526-9696 Bill Vesely SAIC (614) 459-0303 John Boccio BNL
.(516)282-7690 Pranab Samanta BNL (516) 282-4948 Cenny Farrar Commonwealth Edison (312) 294-8530 Tom Tipton NUMARC (202)872-1280 Rich Emch NRC/0TSB (301) 492-96I)1 Ed Butcher NRC/0TSB (301) 492-8393 Millard Wohl NRC/0TSB (301)492-7458 George Bozoki BNL (516) 282-7221 Bob Fitzpatrick BNL (516) 282-7204 David Fischer NRC/0TSB (301)492-7465 l
l l
._