ML18043A702
| ML18043A702 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/03/1979 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 7905250364 | |
| Download: ML18043A702 (3) | |
Text
- ;
consumers Power company General Offices: 21!2 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 May 3, 1979 Mr Jam.es G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
IE BULLETIN 79-07 Consumers Power Company's response to IE Bulletin 79-07 was discussed with Mr E:oward J Wong of your office on May 1, 1979 and is stated below in its
, entirety:
ITEM 1 Identify which, if any, of the methods specified below were ~~ployed or were used in computer codes for the seismic analysis of safety related piping in your plant and provide a list of safety systems (or portions thereof) affected:
Response Spectrum Model Analysis:
- a.
Algebraic (considering signs) summ.a~ion of the codirectional spatial com-ponents (ie, algebraic summ.ation of the maximum values of the codirectional responses caused by each of the components of earthquake motion at a par-ticular point in the mathematical model).
- b.
Algebraic (considering signs) summation of the codirectional inter mode~
responses (ie, for the number of modes considered, the maximum values of res?onse for each mode summed algebraically).
Time History Analysis:
- a.
Algebraic summation of the codirectional maximum responses or the time dependent responses due to each of the components of earthquake motion acting simultaneously when the earthquake directional motions are not statistically independent.
J 7
2
Response
None of the methods specified above were employed or were used in computer codes for the seismic analysis of safety-related piping at the Palisades Plant.
ITEM 2 Provide complete computer program listings for the dynamic response analysis portions for the codes which employed the techniq_ues identified in Item 1 above..
Response
Not applicable since response to Item 1 is "none."
ITEM 3 Verify that all piping computer programs were checked against either piping benchmark problems or compared to other piping computer programs.
You are req_uested 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 programs yielded appropriate results (ie, gave results which corre-sponded to the correct performance of their intended methodology).
Response
The Palisades piping systems were designed and installed utilizing input from Bechtel Power Company and Combustion Engineering Inc.
The following computer programs and methods of verification were used by Bechtel:
- a.
ME 632 - Has been verified using PISOL, PIPESD and TPIPE.
- b.
ME 101 Has been verified using ME 632, TPIPE and SUPER.PIPE.
- c.
PISOL Has been verified using NUPIPE, PIPESD, ADLPIPE and ME 101.
- d.
NUPIPE Has been verified using ADLPIPE.
(In the verification, the algebraic summation option in ADLPIPE was not used. )
- e.
SAPIPE - Has been verified using PISOL.
- f.
TPIPE
- Has been verified using PISOL and ME 632.
Combustion Engineering Inc did not use any computer codes to combine the effects of the different directions of seismic excitation for Palisades.
The six com-ponents of force or moment and the corresponding piping stresses were calcu-lated separately for each of the three directions of seismic excitation.
Absolute summation of the maximum stresses due to two directions of seismic excitation were calculated manually to define the total seismic effects for combination with stresses due to other appropriate loading conditions.
3 ITEM 4 If any of the methods listed in item 1 are identified, submit a plan of action and an estimated schedule for the re-evaluation of the safety related piping, supports, and equipment affected by these analysis techniques.
Also provide an estimate of the degree to which the capability of the plant to safely with-stand a seismic event in the interim is impacted.
Response
Not applicable since response to Item 1 is "none."
David P Hoffman Assistant Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement