ML20052A695

Summarizes Schedule for Completing Containment Mods & for Submission of Addl Info to Complete Review of Mark I Containment Design,Piping Attached to Containment & Mods to Equipment to Perform Containment Safety Function

ML20052A695
Person / Time
Site:	Fermi
Issue date:	03/23/1982
From:	Youngblood B Office of Nuclear Reactor Regulation
To:	Tauber H DETROIT EDISON CO.
References
NUDOCS 8204290041
Download: ML20052A695 (4)

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PDR JYoungblood LPDR' MRushbrook-NSIC LKintner TIC.

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i Docket No.: 50-341 SHanauer 77 c3 s

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Mr. Harry Tauber y

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Subject:

Completion of Fermi 2 Containment Analyses and Modifications One of the open items in the Ferni 2 Safety Evaluation Report (SER) and its supplerents is Mark I containment analyses. This letter summarizes the schedule.

for completing containnent nodifications and for submission of additional infor-nation needed to complete our review of analyses of (1) the Fermi 2 tiark I containment design which has been.nodified to meet the criteria in HUREG-0661,

" Safety Evaluation Report - Mark I Containment - Long-Tern Progran," July 1980, (2) the piping attached to the containment, and (3) modifications to equipment '

required to perform the containment safety function. These matters were discussed with your representatives in a reeting on March 11, 1982, and in subsequent phone conversations with Mr. A. Lim.

The structural analysis of the modified containment including the torus shell, I

vent lines, vent headers and safety relief valve discharge lines will be provided in a plant unique analysis (PUA) report on or before May 3,1982. The analysis of the safety relief valve discharge piping in the wet well airspace will include an ASME Code Class 1 fatigue analysis. This report will include a description of' hydrodynanic loads used for a loss-of-coolant accident and for actuation of safety relief valves during liniting over-pressure transients. The staff's criteria in NUREG-0661 will be used as a basis for acceptance of analysis riethods and results contained in the PUA. Femi 2 acceptance criteria which deviate fron HUREG-0661 criteria will be identified and appropriately justified. The SER Sections 3.8.1, 3.8.2 and 3.9.3, and SER Supplenent No.1 Sections 3.8.4 and 3.9.3 provide staf f's requirements for this analysis.

The report on the analysis of torus-attached piping systems will be provided in two pha*,es.

An interin report will be provided prior to August 1,1982 to justify initial plant operation. A final report will be provided prior to June 1,1983.

The scheduling of a two-phase report is based on the target fuel load date of Uovember 1982.

If fuel load will occur substantially later, a single final report is preferable to the staff. The SER Section 3.8.1, 3.8.2 and 3.9.3, and SER Supplement flo.1 Section 3.8.4 and 3.9.3 provide staff's requirements for this analysis.

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NRC FORM 3:8 0480; NRCM Cao OFFlCIAL RECORD COPY usopo.i i-m o

?1r. Harry Tauber M 2 31982 The seismic and dynanic qualification results for torus-attached piping and equiprent, including purge and vent valves, under combined containnent hydro-dynamic loads and seismic loads will be provided by August 1,1982. This -

information is needed to complete the review by the !!RC Seisaic Oualification Review Team. Operability of the purge and vent valves will also be shown.

If qualification cannot be completed for all equipment by August 1,1982, justification to support interin operation will be provided and a final report will be submitted by June 1,1983. Staff's requirements are provided in SER Supplerent No. 2, Section 3.10, and in staff's letter dated February 24, 1982.

Acceptable long-tern perfomance of the Ferni 2 containnent depends on nodifications to the safety relief valve (SRV) control systen. A report on the SRV control system modifications will be subnitted fiay 3,1982. The report should include descriptions, logic diagrans, instrumentation drawings and analyses of the effects on overpressurization protection and containment hydrodynanic loads of safety relief valve operation. The effect on containnent loads of sinultaneous opening of two relief valves on second and subsequent valve pops due to a single failure should be considered. A comitnent should be provided to conplete nodifications prior to fuel load.

A report on nodifications to the vacuun breakers between the torus and dryvell will be subnitted prior to August 1, 1982. The report should include results of the GpE Controls Owners Group evaluation and 7:UTECH tests. A connitnent should be provided to complete modifications prior to a certain date.

If modifications cannot be completed prior to fuel load, the acceptability of interin operation should be included in the report.

All codifications to the centain"ent including the torus shell, vent lines, vent headers and SRV discharge lines will be conpleted prior to fuel load. Torus-attached piping nodifications and modifications required to qualify torus-attached equipment will be completed prior to startup following the first refuelino.

During plant startup tests, the local temperatures in the pool cause1 by operation of the safety relief valves will be detemined by testing as described in fiUREG-0661.

The Ferni 2 containnent plant unique analysis and associated piping and equipnent analyses will be audited by the staff and its consultants at Brookhaven flational Laboratory and Franklin Institute. please provide 34 copies of these analyses and any subsequent revisions to these analyses to the MRC, and provide 2 copies directly to each of the following addressees:

Brookhaven flational Laboratory puildinq 130 Upton, '!ew York 11973 ATTU: George Maise omce) su m uch our>

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Hr. liarry Tauber W 23W Benjamin Franklin Institute Benjamin Franklin Parkway Philadelphia, Pennsylvania 19103 ATTN: William Segraves Please advise L. L. Kintner, the project nanager, of any significant changes to this schedule, so that we nay revise our review schedule.

Sincerely, I

'Ortpinai sisned by:

Spottswood Burwell 0 B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing cc: See next page g.. >L.p#.1,y' I DL..:.L. B#. ('...

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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. Farner Project Manager - Fermi 2 The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Mr. Larry E. Schuerman l

Detroit Edison Company 3331 West Big Beaver Road Troy, Michigan 48084 t

1 David E..Howell, Esq.

3239 Woodward Avenue Berkley, Michigan 48072 Mr. Bruce Little U. S. Nuclear Regulatory Commission

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Resident Inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 Dr. Wayne Jens Detroit Edison Company 2000 Second Avenue 6--

Detroit, Michigan 48226 Mr. James G. Keppler Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 O

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