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s PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 1881 1981 PHILA D ELPHI A. PA.1910' (2158841-5003 JOSEPH W. GALLAGHER e6actanc e.o"oucr o'= ospaarvant | |||
'"^ | |||
June 3, 1981 Re: Docket Nos. 50-277 50-278 IE Bulletin 79-07 | |||
e6actanc e.o"oucr o'= ospaarvant June 3, 1981 Re: Docket Nos. 50-277 50-278 IE Bulletin 79-07 | \\ \\ ^t /,, | ||
4\\ | |||
o- | o- | ||
: 2) E .*,'J 3 7g g *, 7e | : 2) E.*,'J 3 7g g *, 7e Mr. Boyce H. Grier, Director Office of Inspection & Enforcement 64 | ||
Region I | \\c CUI$$ Wear ? | ||
Region I | |||
'@f',x United States Nuclear Regulatory Commission | |||
,J 631 Park Avenue x.A N, | |||
King of Prussia, PA 19406 | |||
'J I :: i "j, | |||
==Dear Mr. Grier:== | ==Dear Mr. Grier:== | ||
Your letter of April 14, 1979,. forwarded IE Bulletin 79-07, Seismic Stress Analysis of Safety-Related Piping. | |||
Your letter of April 14, 1979,. forwarded IE Bulletin 79-07, | Our letter of | ||
Seismic Stress Analysis of Safety-Related Piping. Our letter of April 24, 1979, provided complete responses to all items in your letter except for Item 3. The following information completes our response to IE Bulletin 79-07. The " Action to be Taken" for Item 3 and our response follow. | ~ | ||
Action To Be Taken | April 24, 1979, provided complete responses to all items in your letter except for Item 3. | ||
The following information completes our response to IE Bulletin 79-07. | |||
The " Action to be Taken" for Item 3 and our response follow. | |||
Action To Be Taken 3) | |||
Verify that all piping computer programs were checked against either piping benchmark problems or compared to other piping computer programs. | |||
You are requested to identify the benchmark problems and/or the computer programs that were used for such verifications or describe in detail how it was determined that these ograms yielded appropriate results e | |||
(i.e., gave results which orresponded to the correct g | |||
performance of their intended methodology). | performance of their intended methodology). | ||
\\pS 1 0 s | |||
e 8106360lT1 | e 8106360lT1 g | ||
~ | |||
Mr. Boyce H. Grier | Mr. Boyce H. Grier Page 2 | ||
===Response=== | ===Response=== | ||
1. | |||
General Electric Company - Nuclear Steam Supply System Computer Programs supplied by EDS Nuclear, Inc.: | |||
Recirculation System - PISOL and SUPERPIPE programs utilized.- | Recirculation System - PISOL and SUPERPIPE programs utilized.- | ||
Main Steam System - PISOL program utilized. | Main Steam System - PISOL program utilized. | ||
Verifications as follows: | Verifications as follows: | ||
(a) | (a) | ||
(b) | EDS has benchmarked both PISOL and SUPERPIPE against the ASME Benchmark Problem 1. | ||
Several such studies have been performed. In the most recent effort, a series of benchmark tests were conducted to compare SUPERPIPE against the | This problem is described in the ASME publication, " Pressure Vessel and Piping 1972, Computer Programs Verification." | ||
following piping analysis programs: | This publication utilized the ANSYS and WESTDYN programs. | ||
r l | (b) | ||
EDS has benchmarked both PISOL and SUPERPIPE against other programs availt.bla to the industry. | |||
Several such studies have been performed. | |||
In the most recent effort, a series of benchmark tests were conducted to compare SUPERPIPE against the following piping analysis programs: | |||
PISOL, NUPIPE, | |||
~~ | |||
PIPESD, and ADLPIPE. | |||
Prior to this, EDS performed benchmarks against John Blume's PIPESD and the Bechtel Power Corporation's ME-101 program. | |||
r l | |||
(c) | |||
For certain seismic options, hand calculations have l | |||
been performed and compared to computer results. | |||
l In the seismic area, the simplified models are typically cantilever and single span configurations. | l In the seismic area, the simplified models are typically cantilever and single span configurations. | ||
(d) | (d) | ||
Such comparisons are used tc show program modifications are properly performing while not impacting other options within the program. These comparisons are described and maintained within the l | The most common benchmark method utilized by EDS is to compare results from one version to another. | ||
Such comparisons are used tc show program modifications are properly performing while not impacting other options within the program. | |||
These comparisons are described and maintained within the l | |||
quality assurance files of the program. | |||
2. | |||
Colt Industries, Inc. - Diesel Generator Piping Systems | |||
- The computer programs utilized are as follows: | |||
+ | |||
nr. Boyce H. Grier | nr. Boyce H. Grier Page 3 a. | ||
A033 - General Purpose Eigen Value Calculation b. | |||
MOFOR - Modal Force Calculation c. | |||
SPIN - Static and Dynamic Analysis of Beams d. | |||
SAGS - Static Analysis of General Structures SPIN and SAGS are public domain programs written by and available through Structural Dynamics Research Corporation (SDRC). | |||
The above computer programs have been verified and found to give correct and accurate answers. The verification methods were as follows: | The above computer programs have been verified and found to give correct and accurate answers. | ||
The verification methods were as follows: | |||
a. | |||
A033 was initially written and verified by IBM. | |||
Colt applied program and subsequently reverified by analysis of representative four degree system. | Colt applied program and subsequently reverified by analysis of representative four degree system. | ||
Substitution of program results into original eigen-value equation showed that the equation was satisfied and that the eigen vectors were orthogonal, | Substitution of program results into original eigen-value equation showed that the equation was satisfied and that the eigen vectors were orthogonal, b. | ||
MOFOR was written by Colt and verified by hand calculations of typical data sets. | |||
c. | |||
SPIN was written and verified by SDRC. | |||
Verification was by comparison with hand calculations of various beams for which classical strength of mate, rial solutions exist. | Verification was by comparison with hand calculations of various beams for which classical strength of mate, rial solutions exist. | ||
d. | |||
SAGS was written and verified by SDRC. | |||
The verification compared program results to hand calculations and to other public domain results (NASTRAN, etc.). | |||
Colt also verified the program by l | |||
comparison to hand classical calculation of eight I | |||
members frame section. | members frame section. | ||
We regret the delay in providing the remainder of this information for IE Bulletin 79-07. Should ycu have any questions or require additional information, please do not hesitate to contact us. | We regret the delay in providing the remainder of this information for IE Bulletin 79-07. | ||
Very truly yours, l | Should ycu have any questions or require additional information, please do not hesitate to contact us. | ||
Very truly yours, WUvk l | |||
cc: United States Nuclear Regulatory Commission l | 6 l | ||
cc: United States Nuclear Regulatory Commission l | |||
Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555 l | |||
1}} | 1}} | ||
Latest revision as of 10:40, 23 December 2024
| ML20004E932 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom |
| Issue date: | 06/03/1981 |
| From: | Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-07, IEB-79-7, NUDOCS 8106160192 | |
| Download: ML20004E932 (3) | |
Text
I
~
s PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 1881 1981 PHILA D ELPHI A. PA.1910' (2158841-5003 JOSEPH W. GALLAGHER e6actanc e.o"oucr o'= ospaarvant
'"^
June 3, 1981 Re: Docket Nos. 50-277 50-278 IE Bulletin 79-07
\\ \\ ^t /,,
4\\
o-
- 2) E.*,'J 3 7g g *, 7e Mr. Boyce H. Grier, Director Office of Inspection & Enforcement 64
\\c CUI$$ Wear ?
Region I
'@f',x United States Nuclear Regulatory Commission
,J 631 Park Avenue x.A N,
King of Prussia, PA 19406
'J I :: i "j,
Dear Mr. Grier:
Your letter of April 14, 1979,. forwarded IE Bulletin 79-07, Seismic Stress Analysis of Safety-Related Piping.
Our letter of
~
April 24, 1979, provided complete responses to all items in your letter except for Item 3.
The following information completes our response to IE Bulletin 79-07.
The " Action to be Taken" for Item 3 and our response follow.
Action To Be Taken 3)
Verify that all piping computer programs were checked against either piping benchmark problems or compared to other piping computer programs.
You are requested to identify the benchmark problems and/or the computer programs that were used for such verifications or describe in detail how it was determined that these ograms yielded appropriate results e
(i.e., gave results which orresponded to the correct g
performance of their intended methodology).
\\pS 1 0 s
e 8106360lT1 g
~
Mr. Boyce H. Grier Page 2
Response
1.
General Electric Company - Nuclear Steam Supply System Computer Programs supplied by EDS Nuclear, Inc.:
Recirculation System - PISOL and SUPERPIPE programs utilized.-
Main Steam System - PISOL program utilized.
Verifications as follows:
(a)
EDS has benchmarked both PISOL and SUPERPIPE against the ASME Benchmark Problem 1.
This problem is described in the ASME publication, " Pressure Vessel and Piping 1972, Computer Programs Verification."
This publication utilized the ANSYS and WESTDYN programs.
(b)
EDS has benchmarked both PISOL and SUPERPIPE against other programs availt.bla to the industry.
Several such studies have been performed.
In the most recent effort, a series of benchmark tests were conducted to compare SUPERPIPE against the following piping analysis programs:
PISOL, NUPIPE,
~~
PIPESD, and ADLPIPE.
Prior to this, EDS performed benchmarks against John Blume's PIPESD and the Bechtel Power Corporation's ME-101 program.
r l
(c)
For certain seismic options, hand calculations have l
been performed and compared to computer results.
l In the seismic area, the simplified models are typically cantilever and single span configurations.
(d)
The most common benchmark method utilized by EDS is to compare results from one version to another.
Such comparisons are used tc show program modifications are properly performing while not impacting other options within the program.
These comparisons are described and maintained within the l
quality assurance files of the program.
2.
Colt Industries, Inc. - Diesel Generator Piping Systems
- The computer programs utilized are as follows:
+
nr. Boyce H. Grier Page 3 a.
A033 - General Purpose Eigen Value Calculation b.
MOFOR - Modal Force Calculation c.
SPIN - Static and Dynamic Analysis of Beams d.
SAGS - Static Analysis of General Structures SPIN and SAGS are public domain programs written by and available through Structural Dynamics Research Corporation (SDRC).
The above computer programs have been verified and found to give correct and accurate answers.
The verification methods were as follows:
a.
A033 was initially written and verified by IBM.
Colt applied program and subsequently reverified by analysis of representative four degree system.
Substitution of program results into original eigen-value equation showed that the equation was satisfied and that the eigen vectors were orthogonal, b.
MOFOR was written by Colt and verified by hand calculations of typical data sets.
c.
SPIN was written and verified by SDRC.
Verification was by comparison with hand calculations of various beams for which classical strength of mate, rial solutions exist.
d.
SAGS was written and verified by SDRC.
The verification compared program results to hand calculations and to other public domain results (NASTRAN, etc.).
Colt also verified the program by l
comparison to hand classical calculation of eight I
members frame section.
We regret the delay in providing the remainder of this information for IE Bulletin 79-07.
Should ycu have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, WUvk l
6 l
cc: United States Nuclear Regulatory Commission l
Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555 l
1