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NOTE TO MEB MEMBERS PWR SUPPORT DATA SHEETS
.I The ACRS has scheduled July 9, 1976 for generic discussion of steam generator and reactor coolant pump supports in order to address the l
allegations raised by the Sun Shipbuilding and Drydock Co. on the ja,4 docket for North Anna Unit 1 and 2.
The Mechanical Engineering Branch kkf is preparing to make the staff presentation.
The Sun allegations are potentially applicable to all other PWR plants f
and therefore ACRS has requested that MEB include in its presentation i
a summary of which plants have similar material and structural config-urations.
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Each member of the MEB is expected to fill out a data sheet for each 4,
~ PWR plant he 'is assigned,'either in the CP, post CP or OL stage.
f/$7J Sheets should be completed by June 25, 1976 and additional information
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is available f rom Kulin Desai or Bob Bosnak.
J. P. Knight, Chief Mechanical Engineering Branch 8.'
Division of Systems Safety b.:. -
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Enclosure:
L As stated cc:
R. Maccary, SS
,j R. DeYoung, PM g'
A. Dronerick, PM t..
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8201200305 810403 PDR FOIA MADDEN 80-515 PDR
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PUR STEAM GENERATOR & REACTOR COOLANT PUMP SUPPORT i
t TABULATION FOR EACH PWR 9WIWWWWWIIB PLANT (Use with Tabulation Sheets) 1.
Design l
1 (a)(1)
What type of support structure was used, i.e., frame, skirt, j
Column.
tp (a)(ii)
If skirt or column structure was used, did it continue 4*,.
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directly to concrete foundation or did it employ a secondary F==u=-
structure to transmit loads to foundation.
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I II.
Material
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(a)
Identify the support (include secondary support if applicable)
I material by ASME or ASTM Specifications (only major support w
members).
t (b)
Indicate supplemental requirements, if any, to material specifi-k
- cation, i.e., [ toughness tests, NDE].
III.
Operation
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What is your estimate of the temperature of structure during operation?
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I PUR STEA:1 CENERATOR & REACTOR COOLM;T ? UMP SUPPORT I
f TABULATION S!!EET (One for Each PWR Plant),
' O' PLANT INFORMATION FROM Specify Utility, AE, etc.
CONTACT 5.....
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pk Phone No.
NM1E OF NRC TABULATOR
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DATE I.
(a)(i)
DESIGN Frame Column Skirt (Circle One)
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OTHER I
,E~'Y (ii)
(If Column or Skirt) Did it employ a Secondary Support p
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~~ ~ Structure YES NO (Circle One)
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MATERIAL h,, ~.
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(a)
List support material ASTM or: ASME Specification W'
(b)'
List supplemental requirements over and above those of material specification if any were used and data is available I
Supplemental YES NO (Circle One)
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If YES, indicate requirement or not available.
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III.
Provide a best estimate of support structure temperature during normal f.
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' operation
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PIlR STENI GENERATOR & REACTOR C00LMiT PUMP SUPPORT TABULATION SilEET w
(One for Each PWR Plant),
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PLANT S$d) A
'2.Df INFORMATION FROM BdM Specify' Utility, AE, etc.
CONTACT TW MAMnt.,
s.w Phone No.
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NAME OF NRC TABULATOR Y (cN
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DATE 4 [/ fr'f~lb h
(Circle One)
I.
(a)(1)
DESIGN Frame Column
- j., E OTilER (ii)
(If Column or Shirt) Did it employ a Secondary Support I
h (Circle One)
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Structure YES I
t I1.
MATERIAL o.
(a)
List support material ASTM or ASME Specification
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C (b)
List supplemental requirements over and above those of material specification if any were used and data is available 7"~ ~
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' Supplemental YES (Circle One)
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If YES, indicate requirement or not available.
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F' III.
Provide a best estimate of support structure temperature during normal p
operation 300 l
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TA3ULATION FOR EACH PWR 954554405E5 PLANT
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(Use with Tabulation Sheets)
I.
Design l
l (a) (1)
What type of support structure was used, i.e., frame, skirt, j
column.
(a)(ii)
If skirt or column structure was used, did it continue r~4.
n.
directly to concrete foundation or did it employ a secondary I
structure to transmit loads to foundation.
[
I II.
Material
~
(a)
Identify the support (include secondary support if applicable) material by ASME or ASTM Specifications (only major support m
I members).
(b)
Indicate supplemental requirements, if any, to material specifi-k
- cation, i.e., [ toughness tests, NDE).
R.c.-
III.
Operation p--
What is your estimate of the temperature of structure'during operation?
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