ML20053E452
| ML20053E452 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/26/1982 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Tauber H DETROIT EDISON CO. |
| References | |
| NUDOCS 8206080170 | |
| Download: ML20053E452 (3) | |
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LB#1 Reading TERA gg 2 61982 MRushbrook NRC/PDR LKintner L/POR 0 ELD NSIC Docket No.: 50-341 I&E TIC HThompson ACRS (16)
SHanauer Hr. Harry Tauber RMattson m
4 Vice President RVollmer g
Engineering & Construction RHartfield, MPA p
Detroit Edison Company 0IE e, d %,_
q 2000 Second Avenue
.% 3. O Detroit, liichigan 48226 2-
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Dear Mr. Tauber:
2
Subject:
fiart I Containment Analyses N
O D
Your April 30, 1982 letter transnitted the Femi 2 Containnent Plant Unf aue Analysis Report as scheduled in our March 23, 1992 letter. We and our consultants have started our review of this report.
Your April 30 transmittal letter stated that the report on safety relief valve control system nodifications would be submitted later than the scheduled date in our March 23 letter.
In conversations with Mr. L. Schuernan we have arrived at a net schedule for submission of this report on safety relief valve control as well as for submission of other information needed to complete our review of the contairraent analyses. This letter surrarizes our current understanding of the scope and schedule for submission of additional information related to the contairinent plant unique analysis.
The following schedule for submission of additional information related to contairunent analyses supersedes the schedule provided in our March 23, 1982 letter.
1.
The torus-attached piping analysis final report will be submitted prior to March 15, 1983. This report will included the final structural analyses for piping systems attached to the torus, considering the motion of the torus under seismic and hydrodynamic loads.
2.
Seismic and dynamic qualification final information for equipment attached to the toms will be provided prior to March 15, 1983. This information will demonstrate that the equipment is qualified to perforn its safety function under the combined seismic and hydrodynamic loads on the contain-nent. Equipment required for safe shutdown should use the Femi 2 site-specific seismic response spectra (see Item 5 below).
t 3.
A report on the safety relief valve ~ control system modifications will be submitted prior to Noventier 1,1982. The report will include a description of the modifications (referred to as the low low set relief logic), logic diagrams, instmeentation drawings, and analyses of the effects of the modified system on containment hydrodynanic loads and on the overpressure _,
protectun analysis.
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Mr. Harry Tauber 4.
A report on modifications to the vacuum breakers between the torus and drywell will be sthmitted prior to August 1,1982. The report will include results of analyses and tests to demonstrate capability to perfom the safety function under accident conditions. A commitment should be provided to complete modifications prior to fuel load.
5.
Information will be submitted prior to March 15, 1983 to demonstrate the adequacy of safety margins for the safety relief valve piping, the torus, and torus-attached piping considering the combination of normal loads and seismic input characterized by the Femi 2 site-specific spectra.
The analysis will use the same assumptions and site specific seismic spectra Alch were used to demonstrate the adequacy of other equipment required for reactor shutdown and continued heat renoval in the event of a major earthquake (Femi 2 Supplementary Seismic Evaluation Report sthmitted May 27,1981).
The Femi 2 Piant Unique Analysis Report indicated that in-plant tests will be used to confirm safety relief valve discharge loads on the torus and on torus attached piping and to establish the maximum local temperature and averageb,
temperature of the pool during safety relief valve discharge. Guidelines for these tests are given in HUREG-0661 (July 1980), NUREG-0763 (May 1981) and NUREG-0783 (scheduled to be issued in June,1982). Provide a description of the test progret prior to August 1,1982, including a description of the tests to be run, a description of test instrumentation, a description of the. model to be used to predict plant unique structure response, and the schedule, relative to initial plant startup tests, for completing the tests and reporting the resul ts.
If there are any questions regarding the scope and schedule for submitting the above information please telephone Mr. L. Kintner, the licensing project manager for Femi 2.
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4 Sincerely, Original signed by *
- 3. J. Youngblood B. J. Youngblood, Chief Licensing Branch No.1 l
Division of Licensing l
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Mr. Harry Tauber
-Vice President Engineering & Construction Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 cc:
Mr. Harry H. Voigt, Esq.
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N. W.
Washington, D. C.
20036 Peter A. Marquardt, Esq.
Co-Counsel The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Mr. William J. Fahrner Project Manager - Fermi 2 The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Mr. Larry E. Schuerman Detroit Edison Company 3331 West Big Beaver Road Troy, Michigan 48084 David E. Howell, Esq.
3239 Woodward Avenue Berkley, Michigan 48072 Mr. Bruce Little U. S. Nuclear Regulatory Commission Resident Inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 Dr. Wayne Jens Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Mr. James G. Keppler Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 5
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