ML20059H650
| ML20059H650 | |
| Person / Time | |
|---|---|
| Issue date: | 01/21/1994 |
| From: | Lyon W Office of Nuclear Reactor Regulation |
| To: | Rosalyn Jones Office of Nuclear Reactor Regulation |
| References | |
| CON-FIN-L-1696-3 TAC-M54946, NUDOCS 9401310072 | |
| Download: ML20059H650 (12) | |
Text
.. _ _ _ _ _ -. _
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January 21, 1994 i
MEMORANDUM FOR:
Robert C. Jones, Chief Reactor Systems Branch Division of Systems Safety and Analysis 2
THROUGH:
Robert. Perch, Acting Chief I
BWR Reactor Systems Section Reactor Systems Branch Division of Systems Safety and Analysis FROM:
Warren C.' Lyon, Sr. Reactor System Engineer l
BWR. Reactor Systems Section Reactor Systems Branch Division of Systems Safety and-Analysis
SUBJECT:
MEETING REPORT - MEETING AT EG&G IDAHO ROCKVILLE OFFICES ON
]
DECEMBER 21, 1993 TO REVIEW EG&G's PRELIMINARY EVENT TREES APPLICABLE TO B&W STEAM GENERATOR TUBE RUPTURE, INEL J08.
CODE L-1696-3, Task 11; TAC M54946 PURPOSE:
Review EG&G's preliminary event trees applicable to B&W i
steam generator tube rupture that have been prepared under INEL Job Code The B&W Owners Group has been continuously developing and improving its emergency operating procedures generic guidance since the staff approved use of the initial version of this guidance in 1983. The staff is completing a review of the version of this guidance that is provided in "The B&W Owners Group Operator Support Committee Emergency Operating Procedures Technical.-
Bases Document," December 31, 1991.
Part of this recent review entails assessment of the B&W-recommended steam generator tube rupture (SGTR) guidance. The staff, as part of this effort,. contracted with EG&G Idaho to provide event trees describing the B&W-recommended guidance and alternatives to that guidance.
The purpose of the meeting was to discuss and assess the first draft of several EG&G event trees. B&W personnel attended the meeting and provided technical feedback regarding anticipated plant operation and behavior.
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Contact:
y W. Lyon, SRXB/DSSA/504-3892 O /d-d L #I ' )
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Robert C. Jones,
1 Areas where improvements were needed were identified.
These included the need for realistic modeling (as contrasted to making conservative assumptions), the need to compare mitigation approaches, and the necessity to consider both i
successful equipment and function recovery as well as subsequent failures while progressing through the event trees.
The EG&G-prepared presentation material, including the preliminary event trees, is attached.
Warren C. Lyon, Sr. Reactor System Engineer BWR Reactor Systems Section Reactor Systems Branch Division of Systems Safety and Analysis DISTRIBUTION Central File PDR R. Jones R. Perch J. Donaghue J. Witter W. Jensen L. Ward EG&G Idaho, Inc.
11426 Rockville Pike Suite 300 Rockville, MD 20852 B. Brooks Babcock & Wilcox
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3315 Old Forest Rd.
Box 10935 Lynchburg, VA 24506
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G:\\MEETB&W.g/94 DOCUMENT NAME:
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B&W Steam Generator Tube Rupture Event Tree Analysis FIN 1696 - Task 11 Idaho National Engineering NRC Project Manager - Brian Thomas (301)-504-1210 NRC Technical Monitor - Warren Lyon (301)-504-3892 Laboratary DOE-ID Technical Monitor - Chuck Noble (208)-526-1369 INEL Program Manager - John H. Bickel (208)-526-9622 INEL Principie investigator - L. Ward (301)-816-7784 1
I Introduction
- Event trees that assess the core damage frequency for a SGTR have been developed for the B&W Technical Basis Guidelines e These event trees were developed by INEL staff experienced in the following areas:
Operations Probailistic Risk Assessment Human Factors Analysis Thermohydraulics e The purpose of this meeting is to review these event trees with B&W and assess potential effective recovery actions
Schedule e The event trees are expected to be completed by January 21,1994 e Core damage frequency analysis is expected to be completed by February 28,1994
- A letter report will be issued describing the results of the analysis on this date SOU 94 92pS4ep
SGTR Event Tree
- Divided into four different scenarios
- Controlled shutdown ET STR-1 Reactor Scram - MSSV cycles successfully ET STR-2 Reactor Scram - MSSV stuck open ET STR-3
- ATWS l
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STR-2 ET Using B&W SGTR EOP.TBD (lli.E-1)
Both steam generators steaming Case 1: Offsite Power Available Case 2: Loss of Offsite Power e Affected SG isolated Case 1: Offsite Power Available Case 2: Loss of Offsite Power
- = - -
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Steam Leak rate <
Operator Reactor MSSV cycles SEQUENCE generator makeup prevents hi-shutdown or successfully DESCRIPTION tube rupture capacity power scram scram SGTR LRG OPA K
MSV STR-1 ATWS Trsfr A STR-2 tbs rR A STR-3 ATWS steam generator tube rupture SGTR.TRE 12-15-93
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