ML17249A899
| ML17249A899 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/29/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR NUDOCS 8005130621 | |
| Download: ML17249A899 (8) | |
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Hr. Leon tlhite, Jr.
Vice President Electric,and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Mr. 'i(hite:
RE:
GINNA PIPING SEISMIC ANALYSIS
. According to the sugary of the meeting held on April 10-11, 1979, at the R. E." Ginna site,.the NRC staff and their consultants requested that RGSE provide existing analyses and isometric drawings of the following mechani.cal distributi on systems:
l., -"A" RHR line'inside containment) 2.
"B" Hain steam line.(inside containment) 3.
Chemical volume control system 4
r
'. 'ample field run of 2" diameter piping - 100 feet The intent of the request was to perform an independent analysis to audit the analytical work previously performed over 10 years ago.
The isometrics were provided to the NRC in transmittals dated October 1, 1979, and February 12, 1980.
In our meeting With RGSE representatives on July 24,
- 1979, we.were informed of.
your seismic upgrading program for Ginna..
Based. on your presentation and your commitment to reanalyze Ginna's piping and supports utilizing the as-built
- drawings, we believe-that a review of the reanalyses-performed will satisfy the NRC safety objective.
- Thus, we request that you submit the following
'nformation for the four piping systems listed above:
l.
Design criteria for the piping seismic upgrade analysis.
This shoUld include:
A.
Computer code,'r other analysis technique, used for the orrIcc3R OURNAIIC3M DATC3N MESTDYN codt, acknowledged
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Mr. Leon D. White APRIL, ~8 t9eo r2e B.'ocumentation of means used to combine the stresses due to three earthquake input co~tpo'nents.
I C;
Floor response spectra. used, and derivation.
I D.
Damping values and load combinations.
E.
Discussion of piping arid pipe support analysis procedures, modeling techniques, assumptions, and acceptance criteria used.
Stress analysis reports, including:
A.
Isometric drawings showing the piping systems, location and type of suppor ts, and val ves'including eccentri'cities).
B.
Tabulation of high piping stress values (including anchors) and identification of the locations where they occur'
- SEE ATTACHED YELLOW FOR PREVIOUS CONCURRENCES C.,Support description and load summary.
We request that within 30 days, you submit your schedule for providing the above information consistent with your current seismi0 upgrade program s chedul e.
This letter'is to confirm'the understanding made in our telephone conver-sation of.March 27, 1980, with RGSE contact on SEP, Mr. George Wrobel.
= DISTRIBUTION:
Sincerely, nea >v J3oeket JRBuchanan'SIC
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Dennis..fl., Crutchfield, Chief Local PDR
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Documentation of means used to combine the stresses due to three earthquake input components.
C.
Floor response spectra
- used, and derivation.
P D.
Damping values and load cottIbinations.
E. -'Discussion of piping and p'ipe support, analysis pro-,
- cedures, modeling techniques, assumptions, and
'cceptancecriteria used-2.
Stress analysis
- reports, including.'.
Isometric drawings showing the piping systems, location and type of suppor'ts, and valves*(including eccentricities).
B.
Tabulation of high 'piping stress values (including anchors) and identification of the location where they occur.
C.
Support description and load summary.
We request. that within 30 days, you submit your schedule for providing the, above information consistent with your current seismic upgrade program schedule.
This letter is to confirm the understanding made in our telephone conver-sation of March 27, 1980, iiith RG8E contact on SEP, Mr-George Wrobel.
, Sincerely, DISTRIBUTION:
Dennis L. Ziemann, Chief Operating Reactors. Brarich No.
'1 Division of Operating Reactors Docket Files SEPB RDG ORB¹2RDG NRR RDG NRC.PDR Local PDR D. Eisenhut B. Grimes R.'ollmer T. J. Carter
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket No. 50-244 April 29, 1980 Mr. Leon Hhite, Jr.
Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Mr. White:
RE:
GINNA PIPING SEISMIC ANALYSIS, According to the summary of the meeting held on April 10-11, 1979, at the R. E. Ginna site, the NRC staff and their consultants requested that RG8E provide existing analyses and isometric drawings of the following mechanical distribution systems:
l.
"A" RHR line (inside containment) 2.
"B" Main steam line (inside containment) 3.
Chemical volume control system 4.
Sample field run of 2" diameter piping - 100 feet The intent of the request was to perform an independent analysis to audit the analytical work previously performed over 10 years ago.
The isometrics were provided to the NRC in transmittals dated October 1, 1979, and February 12, 1980.
In our meeting with RG8E representatives on July 24, 1979, we were informed of your seismic upgrading program for Ginna.
Based on your presentation and your coIImIitment to reanalyze Ginna's piping and supports utilizing the as-built
- drawings, we believe that a review of the reanalyses performed will satisfy the NRC safety objective.
- Thus, we request that you submit, the following information fot the four piping systems listed above:
1.
Design criteria for the piping seismic upgrade analysis.
This should include:
A.
Computer code, or other analysis technique, used for the upgrade
- program, and verification of adequacy.
If the llESTDYN code is being used, this fact needs only be acknowledged.
Mr. Leon D. White 2
April 29, 1980 B.
Documentation of means used to combine the stresses due to three earthquake input components.
C.
Floor response spectra
- used, and derivation.
D.
Damping values and load combinations.
E.
Discussion of piping and pipe support analysis procedures, modeling techniques, assumptions, and acceptance criteria used.
2.
Stress analysis
- reports, including:
A.
1sometric drawings showing the piping systems, location and type of
- supports, and valves (includi ng eccentricities).
B.
Tabulation of high piping stress values (including anchors) and identification of the locations where they occur.
C.
Support description and load summary.
We request that within 30 days, you submit your schedule for providing the above information consistent with your current seismic upgrade program schedule.
This letter is to confirm the under'standing made in our telephone conver-sation of March 27, 1980, with RGI%E contact on SEP, Mr. George Wrobel.
Sin
- rely, nnss M.
rutchfield, Chi Operating Reactors Branch No.
5 Division of Licensing