ML19344F261
| ML19344F261 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/20/1980 |
| From: | Chang Li Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8009150034 | |
| Download: ML19344F261 (4) | |
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August 20, 1980 Dockets Nos. M-317 and 50-318 LICENSEE: Baltimore Gas and Electric Company (BG&E/ licensee)
FACILITY: Calvert Cliffs Nuclear Power Plant (CCNPP), Units Nos. I and 2
SUBJECT:
SUMMARY
OF MEETING HELD ON JULY 17, 1980 TO DISCUSS THE 18 MONTH FUEL CYCLES FOR THE CCNPP-1 & 2 The meeting was held at the Conmission's offices in Bethesda, Maryland. A list of attendees is given in Enclosure 1.
Introduction By letter dated June 26, 1980, BG&E submitted six documents (Statistical Combination of Uncertainties, Parts 1, 2, 3, FIESTA, CEAW, BASSS) as..
requested a review and approval of these documents.
The licensee requested the meeting to present an overview of their submittals.
The slides used in the meeting, containing Combustion Engineering (CE) proprietary information, were submitted by letter from CE dated July 28, 1980.
They were distributed to all the NRC meeting attendees on August' 11, 1980.
Summary After opening remarks by the NRC (Li) to explain the purpose of the meeting, the licensee explained the need for the NRC approval of these documents. The licensee anticipates some degradation in operating margin during its program to increase the operation of the CCNPP units to 18 month cycles.
The sub-mitted reports will recover the margin inherently available in the design but not explicitly taken credit for in their Safety Analysis.
The licensee intends to reference the three volumes of Statistical Combination of Uncertainties in its license application for operation of both units in the next cycles (Fall 1980 for Unit 1 and Spring 1981 for Unit 2). Also, the licensee intends to reference all submitted documents for subse'juent cycles of both units.
CE presented FIESTA and CEAW and also introduced BASSS.
FIESTA is a one-dimensional two-group space-time kinetics code for calculating PWR scram reactivities. The Better Axial Shape Selection System (BASSS) uses the in-core detector system for monitoring the Departure from Nucleate Boiling -
Limiting Condition for Operation (DNB-LCO). CEAW documents the new methods that can be used in analyzing the sequential CEA Group Withdrawal (CEAW) event for CE's analog protected systems.
The Statistical Combination of Uncertainties (SCU) Parts 1 and 3 were addressed by CE.
Items discussed were program objectives, uncertainties of interest for Statistical Combination of Measurement Uncertainties, previous method of applying uncertainties, application of uncertainties with SCU, impact of SCU 8009250
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CCNPP-1 & 2 on margin to DNB-LC0 and results of margin gain. As part of the SCU, the following subjects were discussed:
stochastic simulation methodology, ex-core detector monitored DNB-LC0 uncertainty analysis, stochastic simu-lation of the AF0 LSSS and linear heat rate uncertainty analysis.
CE also presented Part 3 of SCU which includes distinction between state and system parameters, discussion of previous vs. new methods and explana-tion of new methods.
It was concluded that at least 95% probability with at least 95% confidence that the limiting fuel pin will not experience DNB if the MDNBR computed using the new design model is greater than 1.23.
The NRC staff expressed concern that there are limitations for combining uncertainties of parameters which may not be independent.
Previous Safety Evaluations of Westinghouse submittals should provide some guidelines on what is ' acceptable.
The licensee indicated that the three parts of the SCU will be used in the next reload analysis of CCNPP-1.
It is desirable for BG&E to have these three volumes of SCU approved by the end of November 1980.
It was stated that these documents would require a thorough review and the uncertainty of staff availability was high.
Therefore, it seemed to be unrealistic to expect the approval ~so soon. The NRC staff asked if BG&E had any other alternatives.
The licensee felt that it would like to keep working on the new methods as much as possible, rather than to go back to the old method when it was already too late.
In sumary, the main purpose of the meeting, to present an overview of the submitted six documents, was successful. The review schedule difficulties as pointed out by NRC staff remained to be solved later.
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Chang Yang Li, Project Manager Operating Reactors Branch 3 Division of Licensing
Enclosure:
List of Attendees cc w/ enclosure:
See last page t
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LIST OF ATTENDEES Enclosure JULY 17,1980 '
NRC
.C._E_-
' Joy'Mundy P. Kruse Monte Conner D. H. Huber-Lambrois tois-F. J. Berte' Joe Holonich T. Rodak Chang Li C. Lepine Harry Balukjian-William Johnston BG&E Daniel Fieno M. E. Bowman
'Marvin Dunefeld W. J. Lippold
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Walter L. Brooks J. J. Napier L
Dale Powers M. J. Wise H. Richings Larry Kopp
.R. A. Clark L. E. Phillips l
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a-MEETING
SUMMARY
DISTRIBUTION Licensee:
BG&E
- Copies also sent to tho*e people on service (cc) list for subject plant (s).
Docket File NRC PDR L PDR TERA NSIC ORB Rdq NRR Rdg HDenton ECase DEisenhut RPurple RTedesco TNovak-Glainas RReid TIppolito SVarga DCrutchfield RACla rk
-0RB Project Manager -CYLi Licensing Assistant -PKreutzer OELD AE00 - iHeltemes -
p IE-3 SShowe (PWR) or CThayer (BWR), IE RFraley, ACRS.(16)'
Program Support Brar.cli GZech-J01shinski i
NRC. Participants
' Joy Mundy Dale Powers Monte Conner.
M. J. Wise Lambrois Lois H. Richings i
Joe Holonich Larry Kopp Harry Balukjian L. E. Phillips j
William Johnston Daniel Fieno Marvin Dunefeld Walter L. Brooks i
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