ML19225A431: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:_i 4!v DUKE POWER COMPANY 28242 E'.ECTRIC CESTER, BOX 33180, CH ARIMTE, N. C.
{{#Wiki_filter:_
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i 4 !                                                                                   v DUKE POWER COMPANY
, G g-May 29, 1979 e.-- v, c->z:z-o_go_. :o 3$h Mr. J. P. O'Reilly, Direc+or , sion m..y;2 U. S. Nuclear Regulatory t,om6 m 101 Marietta Street, Suite 3100 g:-Atlanta, Georgia 30303 Re: Perkins Nuclear Station 50-488, 50-489, 50-490 Docket Hos.:
  ,                                                                      28242 E'.ECTRIC CESTER, BOX 33180, CH ARIMTE, N. C.
okee Nuclear Station Ket Hos.: 50-491, 50-492, 50-493 4E Bulletin: 79-07 Duke File: P81-1412.ll-1 i  
      ;F.Nd*$".', .                                                         ,
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                                                                                            - v, May 29, 1979                                                             e.-
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                                                                                            . :o 3       $hm Mr. J. P. O'Reilly, Direc+or , sion                                       ..
U. S. Nuclear Regulatory t,om6                                           m       y;2 101 Marietta Street, Suite 3100                                           -      g:
Atlanta, Georgia 30303 Re:     Perkins Nuclear Station50-489, 50-490 50-488, Docket Hos.:
okee Nuclear Station Ket Hos.: 50-491, 50-492, 50-493 4E Bulletin: 79-07 Duke File: P81-1412.ll-1 i


==Dear Mr. O'Reilly:==
==Dear Mr. O'Reilly:==


Enclosed is Duke Power's response to IE Bulletin 79-07.
Enclosed is Duke Power's response to IE Bulletin 79-07.
Very truly yours,... C. Dail Vice President Design Engineering
Very truly yours,
~JDW/jm1 Attach.-ent Nuclear Regulatory Comission cc: Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C.
                                .
20555 bb# []OL,1 , OU"'" 7 90719 0 lld>  
              .. C. Dail Vice President Design Engineering
. ..', e*...DUKE'S RESPONSE TO IE BULLETIN 79-07 FOR PERKINS/ CHEROKEE NUCLEAR STATION
            ~JDW/jm1 Attach.-ent cc: Nuclear Regulatory Comission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C.     20555 bb                   ,          # []OL,1 7 90719 0 lld>
.With respect to items (1), (2) and (4) of the subject bulletin, we respond as followt:
OU"'"
The EDS computer program SUPERPIPE is being and will be used on the piping analysis done on Perkins and Cherokee. The analysis of the primary coolant Both EDS Huclear, Inc.
 
        . ..
    ', e
*
  .
    .
      .
DUKE'S RESPONSE TO IE BULLETIN 79-07 FOR PERKINS/ CHEROKE          .
With respect to items (1), (2) and (4) of the subject bulletin, we respond as followt:
The EDS computer program SUPERPIPE is being and will be used on the piping analysis done on Perkins and Cherokee. The analysis         of the Both EDS     primary Huclear,   coolant Inc.
loop will be performed by Combustion Engineering.
loop will be performed by Combustion Engineering.
and Combustion Engineering have confirmed that their programs do not use algebraic sunination methods for combining responses.
and Combustion Engineering have confirmed that their programs do not use algebraic sunination methods for combining responses.
In answer to paragraph (3) of IE Bulletin No. 79-07, the verification Due to the of computer programs was done in a combination of ways.
In answer to paragraph (3) of IE Bulletin No. 79-07, theDue verification to the of computer programs was done in a combination of ways.
non-existence of the ASME benchmark problems during the time of the original analyses, original versions of programs were verified with hand calcu-As more and more programs became cocinercially available, lated results.
non-existence of the ASME benchmark problems during the time of the original analyses, original versions of programs were verified with hand calcu-lated results. As more and more programs became cocinercially available, comparisons were made with these programs and with the ASME problems.
comparisons were made with these programs and with the ASME problems.
Specifically, EDS has used a combination of any or all of the following methods:
Specifically, EDS has used a combination of any or all of the following methods: 1.Cocparison to ASME Benchmark Problem #1
: 1. Cocparison to ASME Benchmark Problem #1         ,
, Benchmark Problems Utilizing EDS Programs and Other Industry 2.Programs (PIPESD,HUPIPE,ME-101) 3.Comparison to Hand Calculations 4.Comparison Between EDS Programs and Updated Versions In answer to paragraph (3) of IE Bulletin 79-07. Coctustion Engineering responds as follows: " Time histories of the six components of force or moment (Fx, Fy, Fz, Mx, My, Mz) at various sections of the reactor coolant system main loop piping were computed separately for each of two horizontal and the vertical The maximum co-directional components directions of seismic excitation.
: 2. Benchmark Problems Utilizing EDS Programs and Other Industry Programs (PIPESD,HUPIPE,ME-101)
of force or moment over all time from each of the three directions of excitation were combined by the square-root-of-the-sum-of-the-squares method to define the seismic loading condition at the particular piping The load sets thus defined were compared to, and shown to be location.less governing than, the seismic loadings specified for design of the piping.Since the cocbination of loads were performed after the completion of propriateness of the dynamic analysis portion of the computation, the results of the corbination was verified by di.2ct observation of the uncombined inputs and the combined outputs."-j;/Ih ,}}
: 3. Comparison to Hand Calculations
: 4. Comparison Between EDS Programs and Updated Versions In answer to paragraph (3) of IE Bulletin 79-07. Coctustion Engineering responds as follows:
              " Time histories of the six components of force or moment (Fx, Fy, Fz, Mx, My, Mz) at various sections of the reactor coolant system main loop piping were computed separately for each of two horizontal and the vertical The maximum co-directional components directions of seismic excitation.
of force or moment over all time from each of the three directions of excitation were combined by the square-root-of-the-sum-of-the-squares method to define the seismic loading condition at the particular piping location. The load sets thus defined were compared to, and shown to be less governing than, the seismic loadings specified for design of the piping.
Since the cocbination of loads were performed after the completion of propriateness of the dynamic analysis portion of the computation, the results of the corbination was verified by di.2ct observation of
                                                                          -
the uncombined inputs and the combined outputs."
j;/   Ih           ,}}

Revision as of 10:40, 19 October 2019

Responds to IE Bulletin 79-07.SUPERPIPE Computer Program Used on Piping Analysis.Primary Coolant Loop Analysis Will Be Performed by C-E.Will Not Be Used.Algebraic Summation Methods for Combining Responses
ML19225A431
Person / Time
Site: Perkins, Cherokee  Duke Energy icon.png
Issue date: 05/29/1979
From: Dail L
DUKE POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 7907190176
Download: ML19225A431 (2)


Text

_

i 4 ! v DUKE POWER COMPANY

, 28242 E'.ECTRIC CESTER, BOX 33180, CH ARIMTE, N. C.

F.Nd*$".', . ,

-

G g

- v, May 29, 1979 e.-

c-

z

>z

-o

_

_ go

. :o 3 $hm Mr. J. P. O'Reilly, Direc+or , sion ..

U. S. Nuclear Regulatory t,om6 m y;2 101 Marietta Street, Suite 3100 - g:

Atlanta, Georgia 30303 Re: Perkins Nuclear Station50-489, 50-490 50-488, Docket Hos.:

okee Nuclear Station Ket Hos.: 50-491, 50-492, 50-493 4E Bulletin: 79-07 Duke File: P81-1412.ll-1 i

Dear Mr. O'Reilly:

Enclosed is Duke Power's response to IE Bulletin 79-07.

Very truly yours,

.

.. C. Dail Vice President Design Engineering

~JDW/jm1 Attach.-ent cc: Nuclear Regulatory Comission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C. 20555 bb , # []OL,1 7 90719 0 lld>

OU"'"

. ..

', e

.

.

.

DUKE'S RESPONSE TO IE BULLETIN 79-07 FOR PERKINS/ CHEROKE .

With respect to items (1), (2) and (4) of the subject bulletin, we respond as followt:

The EDS computer program SUPERPIPE is being and will be used on the piping analysis done on Perkins and Cherokee. The analysis of the Both EDS primary Huclear, coolant Inc.

loop will be performed by Combustion Engineering.

and Combustion Engineering have confirmed that their programs do not use algebraic sunination methods for combining responses.

In answer to paragraph (3) of IE Bulletin No. 79-07, theDue verification to the of computer programs was done in a combination of ways.

non-existence of the ASME benchmark problems during the time of the original analyses, original versions of programs were verified with hand calcu-lated results. As more and more programs became cocinercially available, comparisons were made with these programs and with the ASME problems.

Specifically, EDS has used a combination of any or all of the following methods:

1. Cocparison to ASME Benchmark Problem #1 ,
2. Benchmark Problems Utilizing EDS Programs and Other Industry Programs (PIPESD,HUPIPE,ME-101)
3. Comparison to Hand Calculations
4. Comparison Between EDS Programs and Updated Versions In answer to paragraph (3) of IE Bulletin 79-07. Coctustion Engineering responds as follows:

" Time histories of the six components of force or moment (Fx, Fy, Fz, Mx, My, Mz) at various sections of the reactor coolant system main loop piping were computed separately for each of two horizontal and the vertical The maximum co-directional components directions of seismic excitation.

of force or moment over all time from each of the three directions of excitation were combined by the square-root-of-the-sum-of-the-squares method to define the seismic loading condition at the particular piping location. The load sets thus defined were compared to, and shown to be less governing than, the seismic loadings specified for design of the piping.

Since the cocbination of loads were performed after the completion of propriateness of the dynamic analysis portion of the computation, the results of the corbination was verified by di.2ct observation of

-

the uncombined inputs and the combined outputs."

j;/ Ih ,