ML20198R566
| ML20198R566 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/31/1997 |
| From: | Karavoussianis STEVENSON & ASSOCIATES |
| To: | |
| Shared Package | |
| ML20198R571 | List: |
| References | |
| 93C2799-C-018, 93C2799-C-018-R00, 93C2799-C-18, 93C2799-C-18-R, NUDOCS 9901080227 | |
| Download: ML20198R566 (16) | |
Text
ision /
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CALCULATION TITLE PAGE Total Number of Pages: 16 Seismic Capacity of the RBCCW Heat Exchangers TITLE 1
N/A 0
93C2799-C-018 CALCULATION #
REVISION No #
VENDOR CALCULATION NUMBER CCR 2330A CS HXR System Name System Number Structure Component
)
NUCLEAR INDICATOR:
Calc. Supports 3 CATI O RWQA O
SB00A DCR/MMOD?
4 O FPQA O ATWSQA O
NON-QA O Yes g No DCR/MMOD No Cale. Supports Calc. Supports Licensing?
4 Ind. Analysis?
4 0 Yes a No O Ye5 0 No Chg. Doc. Ref.
Reference INCORPORATES:
Affects DBS?
CCN NO:
AGAINST REV.
esp.
N/A N/A O Yes g No Reference Executive Summary (This NU Calculation is generated to enter the attached S&A calculation into NU's document control / tracking system, and to document the current NU technical review. This S&A calculation is part of NU's IPEEE program.)
l This calculation evaluated the sejsmic capacity of the RBCCW Heat Exchangers (X18A, X18B & X18C). The result is a high-confidence oflow probability of failuw (HCLPO capacity in terms of PGA. The liCLPF capacity of these heat exchanger is 0.29g PGA. This capacity is used in the seismic margin assessment.
Approvals (Print / Signature)
Prepaier:,
j; Date:
Apostolos Karavoussianis
/f.
whM
/t,/2o/9iL Interdiscipline Reviewer:
Date:
N/A Discipline:
p/A p///
Interdiscipline Reviewcr:
Date:
N/A Discipline:
g//)
p//7 Date:
Independent Reviewe[r:MN MI,Rrk.,/
/J1/.3//M
-=
s Nabil Jura,dini te e ai io
//>
o Installation VeriGentio{ {Calculatfori accurately represents actual field conditions or does not affect plant contipuratiorp
/A/1//?f Preparer / Designer Engineer: A/AArs. Tie,% v A M / Md 46fA D:te:
9901080227 981231 id PDR ADOCK05000336]
p PDRSL
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DCM FORM 5-1 A Rev.06
,q g {07'Y$
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c ge
CTP/ Passport DATADASE INPUTS Page lA of Il Cr.lculation Number:
N/A Revision:
N/A (prefix)
(sequence no.)
(suffix)
Vendor Calculation Number /Other: 93C2799-C-018 Revision:
O CCN#
N/A QA @ Yes O No Calc Voided:
0 Yes
@ No Superseded By:
N/A Supersedes Cale:
N/A Discipline (Up to 10)
L,N,Q Unit Project Reference Component Id Computer Code Rev. No./
(EWA)
Level No.
02 M2-94223 X18A N/A N/A X18B X18C
~
PMMS CODES
- Structure System Component Reference C91culation Rev No.
9 -C-G-R D CCR HXR 93C2799-C-005
-N W l hl,ht l
- The codes required must be alpha codes designed for structure, system and component.
Reference Drawing Sheet Rev. No.
25203-29004 20 N/A 25203-11990 N/A N/A l
4 I
Comments:
None DCM FORM 5-1B 4
Rev 06 Pageiof1 i
- a _
1
' NORTHEAST UTILITIES SERVICE COMPANY 1
I
SUBJECT:
Seismic Capacity of the RBCCW Heat Exchangers By:
A. Karavoussianis Date: 12/20/97
' Chkd:
N. Juravdini Date: 12/20/97 Calc. No. 93C2799-C-018 Rev.! O Sheet No. IB = of II TABLE OF CONTENTS.
.. SECT 7QN '
PAGE No,
-)
NU Calculation Title Page 1
CTP Data Base Inputs lAT
'I
~ NU Table of Contents 1B Calculation Review Comment and Resolution Form 1C S&A Calculation Cover Sheet ID
- S&A Calculation:
- 1. Introduction & Summary 1E 2.. References.
-1E-
- 3. : Configuration, Criteria and Assumptions 2
4,~ Calculation 2 - ll Total. Number of Pages 16 pages E
e[
1-j..
s v
}--
p g - - -. - --
y-.c
- Calculation Review Comment and Resolution Form (Sheet 1 of I).
-Calculation Number: 93C2799-C-018 Revision: 0 Calculation
Title:
Seismic Capacity of the RBCCW Heat Exchangers Calc. Originator: Apostolos Karavoussianis Reviewer (PRINT): Nabil Juraydini l
This form is intended to document significant comments and their resolutions. Typographical errors and other editorial recommendations may be marked up in the calculation text and presented to the originator Review Type 0 OInterdiscipline
@ Independent Reviewer (SIGN) flQ 4kyy Date:
43fsr/7A v
i y
(signature signifies all comments have been resolved to your satisfaction) i ite m Page/Section Comments
Response
1 of 1 N/A This NU Calculation is generated to enter the attached S&A calculation into NU's document control / tracking system, and to document the current NU technical review. This S&A calculation is part of NU's IPEEE program.
There are no technical or significant review comments which need to be document here. Only S&A's calculation cover sheet is numbered as page 1D (this page was not numbered by S&A), and S&A calculation's first pages is re-numbered as 1E. These changes are for page numbering purposes only.
DCM FORM 5-1C Page IC Rev.06 Page1 ofI
93C2799-C-018 PAGE iD
~
')
Clicot:
NO Calculation No.
Col 8
..Titu Seismic C%.c4, d&
AB ccw Neal
[4 e han g-o v
Project:
MP2.
TPI//
Method:
See insio4 i
i l
Acceptance Criteria:
$a in 6th i
Remarks:
')
4 l
REVISIONS No.
Description By Date Chk.
Date App.
Date
)
0 Initial Issue i l p, p gA si//g/95 N$b lI//6/$ [j]/)
/hh y
1 CALCULATION S
COVER CONTRACT NO.
SHEET 93C 2.7 c)c)
- ===8"=
MGURE 13 l
1-20
JOB NO. 93C2799 Sheet iE
SUBJECT:
C018 '
Rev.O STEVENsON Seismic Capacity By<=g6n//5/6
- f.'d"8' of the RBCCW Heat Exchangers n,.
ChldASL7 U/j'6/9C 1 Introduction & Summary This calculation evaluates the seismic capacity of the Millstone Point Unit 2 Reactor Building Component Cooling Water Heat Exchangers, equipment ids XI8A, XI8B, XI8C. The result is a high-confidence oflow probability of failure (HCLPF) capacity in terms of peak ground acceleration (PGA). The results are to be used in the seismic margin assessment of MP2. Refer to NP-6041 (reference 1) for a discussion of a seismic margin assessment and HCLPF.
Summary ofResults The capacity of each RBCCW Hx in terms of PGA is 0.29g. This value is a HCLPF capacity as defined in NP-604' Capacity is controlled by anchorage shear.
2 References 1.
A Methodology for Assessment of Nuclear Pqwer Plant Seismic Margin, Electric Power Research Institute, prepared by Jack R. Benjamin and Associates, Inc., et al.,
August 1991. NP-6041-SL, Revision 1.
2, Generic Imnlementation Procedure for Seismic Verification of Nuclear Plant Equipment. Revision 2, Seismic Qualification Utility Group, February 1992.
3.
NU drawings; 25203 series (individual drawings referenced by extension number in body of calculation).
4.
" Code Requirements for Nuclear Safety Related Concrete Structures", ACI 349-90, American Concrete Institute.
5.
" Building Code Requirements for Reinforced Concrete", ACI 318-89, American Concrete Institute.
j 6.
" Manual of Steel Construction",9th Edition, American Institute of Steel Construction.
l-7.
S&A calculations forjob 93C2799.
8.
Seismic Verification of Nuclear Plant Eauioment Anchorage (Revision 11 Volume 4.
Electric Power Research Institute, prepared by URS/ John Blume & Associates, June 1991. NP-5228-SL, Revision 1..
- 9.
S&A document received 93C2799-DC-024.
10.
Blevins, R.," Formulas for Natural Frequency and Mode Shape",1979.
i V
4
JOB NO. 93C2799 Sheet 2.
S*A
SUBJECT:
C018 Rev.o s e so Seismic Capacity By% u/'g/W of the RBCCW Heat Exchangers Chk'M E t % I T r
3 Configuration, Criteria and Assumptions The configuration is shown in the following sheets and was obtained from referenced drawings.
The evaluation is based on the guidance of NP-6041, as outlined in Section 6 of that document.
' Seismic demind is per S&A calculation 93C2799-C005.
Based on the IPl.2E walkdown and A-46 walkdown and screening results, attached piping is well restrained [9]. Therefore no piping loads are included.
Assumptions
. - Yield stress of saddle material is assumed to be 30 ksi
%& % oM u<dte pM.-s, v..<lu J %.v~u s~ddle pt Ju-O % " a,r'd.
e 4 Calculation Capacity calculations are contained in the following pages.
4
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