NUREG/CR-5320, Summary of 890518 Meeting w/C-E Owners Group Re Reactor Vessel Support Embrittlement Discussed in NUREG/CR-5320, Impact of Radiation Embrittlement on Integrity of Pressure Vessel Supports for Two PWR Plants. Viewgraphs Encl
ML20244E271 | |
Person / Time | |
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Issue date: | 06/13/1989 |
From: | Chan T Office of Nuclear Reactor Regulation |
To: | Office of Nuclear Reactor Regulation |
References | |
RTR-NUREG-CR-5320 NUDOCS 8906200240 | |
Download: ML20244E271 (17) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION -
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WASHINGTON, D. C. 20555 e
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June 13, 1989 ORGANIZATION:
COMBUSTION ENGINEERING OWNERS GROUP (CEOG)
SUBJECT:
MEETING
SUMMARY
- REACTOR VESSEL SUPPORT EMBRITTLEMENT On May 18, 1989, the staff and its consultants met with representatives of the CEOG to discuss the NRC's review of reactor vessel (RPV) support embrittlement, as discussed in NUREG/CR-5320, " Impact of Radiation Embrittlement on Integrity of Pressure Vessel Supports for Two PWR Plants." The objective ot the meeting was (1) to identify plants which have supports similar to the two plants used in the staff's study and mi life of the plant, and (2) ght have a concern for their interity during the to provide a plan for resolving the concern for RPV support integrity for those affected plants.
A list of attendees is provided as Enclosure 1; a copy of the meeting handouts is provided as.
The CE0G stated quantitatively that each of their licensees determined that the structural integrity of their respective RPV supports was not of concern, taking into account the effects of neutron induced embrittlement. The CE0G displayed several sketches of typical suppo~rt configurations, but did not address in any quantitative detail, plant specific questions related to RPV support configura-tions or the results of licensee studies. The CEOG also stated that it had not independently reviewed the licensees studies.
l Utilizing the NUREG/CR screening criteria, the CE0G concluded that j
(a) the short column supports at CE plants are in compression, and are therefore not of concern, i
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(b) the plant with the shield tank support has been analyzed e.nd i
is not of concern, and i
(c) analyses of long column supports that are in mild tens. ion, show that they are not of concern.
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8906200240 990613TOPRPENVCg',
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.. June 13, 1989 The staff indicated that quantitative information regarding support structure configuration and analyses results would be needed in order to gain a better understanding of the RPV supports' accept lity.
p D
erence L. Chan, Senior Project Manager krojectDirectorateV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation cc: Mr. Charles B. Brinkman Combustion Engineering Inc.
12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Edward Sterling Combustion Engineering Inc.
c/o Arizona Public Service Co.
P.O. Box 52034 Phoenix, Arizona 85072-2034 See next page CONTACT:
1erence L. Chan, NRR 492-3062
l l
" June 13, 1989 The staff indicated that quantitative information regarding support structure configuration and analyses results would be needed in order to gain a better understanding of the RPV supports' acceptability, original signed by Terence L. Chan, Senior Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation cc: Mr. Charles B. Brinkman Combustion Engineering Inc.
12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Edward Sterling Combustion Engineering Inc.
c/o Arizona Public Service Co.
P.O. Box 52034 Phoenix, Arizona 85072-2034 See next page DISTRIBUTION
- Docket File, A. Mendiola NRC & LPDRs' B. Boger PDS Reading JSniezek GKnighton TChan 0GC EJerdan BGrimes NRC Participants ACRS(10)
MJohnson(17D19)
CONTACT:
Terence L. Chan, NRR 492-3062 t s DRSP/PD5 D
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6/n /89 6/g/89 0FFICIAL RECORD COPY
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ENCLOSURE 1 LIST OF ATTENDEES NRC/CEOG MEETING ON REACTOR VESSEL SUPPORT EMBRITTLEMENT May.18' 1989
-i T. Chan R. Borsum, Babcock & Wilcox B. Elliot D.' Williams, Arkansas Power & Light R. Johnson A. Wyche, SERCH Licensing /Bechtel C. Hrabal B. Hopkins, Bechtel Power Corp.
S. Lee G. Doney..Coahostion Engineering A. Taboada P. Richardson, Combustion Engineering P. Randall M. Mcdonald, Combustion Engineering J. O' Brian 1
l M. Mayfield 1
l C. Cheng
.i G. Bagchi D. Jeng J. Ma Wm. Pennel (ORNL)
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