ML20011E359
| ML20011E359 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 02/06/1990 |
| From: | Stang J Office of Nuclear Reactor Regulation |
| To: | Sylvia B DETROIT EDISON CO. |
| Shared Package | |
| ML20011E360 | List: |
| References | |
| TAC-65975, NUDOCS 9002130291 | |
| Download: ML20011E359 (4) | |
Text
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- UNITED STATES
", j NUCLEAR RESULATORY COMMISSION i i
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P Docket No. 50 341 l
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Mr.- B.iRalph Sylvia Senior Vice' President - Nuclear i
Operations i
C Detroit Edison Company.
6400 North Dixie Highway _
Newport, Michigan 48166 4
Dear.Mr. Sylvia:
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SUBJECT:
RELIEF REQUEST TO THE INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES' (TAC NO.-65975)
.By' letter dated December 6, 1988, Detroit Edison Company (DECO) requested relief from ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition, Winter r
Addendum 1981,4 The December 6, 1988, request superseded DECO relief requests dated September 20, 1985 and July 31, 1987.
The request specifically requests relief'for 34 valve groups involving 84 containment isolation valves from the requirements to perform Category A Containment Isolation Air Leakage Tests on i
each valve individually as required by Subsection IWV, Article IWV 3000,
' Paragraphs 3426 and 3427 the ASME Section XI, Boiler and Pressure Vessel Code.
The NRC staff.has reviewed the Deco request for relief for the 84 valves and Lfinds it acceptable with the exception of valve E11-F408'and assignment of 1
. leakage limits for penetrations as' set forth in the. enclosed Safety Evaluation.
By letter dated November 15, 1989, DECO committed to individually test valve j
'E11-F408 in all-future required-tests rather than in a group as proposed in the December 6,~1988, relief request.
The staff has reviewed the licensee's commitment;and finds it acceptable, j
In the November 15, 1989, letter Deco addressed the. staff concern dealing with
- the. administrative leak limits assigned to a penetration.
DECO committed to i
re-evaluate the-administrative limits for leak rates assigned to each penetra-
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tion;to make'sure all valves in the penetration ~are considered individually J
rather.than the simple sum of the leak rate for each valve in the penetration.
The staff has reviewed the licensee's commitment and finds it acceptable.
A In'accordance with Technical Specification 4.0.5, written relief must be obtained from the Commission pursuant to 10 CFR 50.55a(g)(6)(i), for deviations from Section XI of the ASME Code.
Our review has determined that the code requirements for-the specified valves are impractical, that the granting of the relief is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest; giving due consideration to the burden upon the licensee that could result if the requirements were imposed gpgg teS$p r
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s Lon the facility, i Accor'dingly,- relief is granted, from the requirements. of. ASME-iCode,'Section XI,1980 Edition, Winter 19811 Addendum, Subsection IWV, Article-IWV;3000, Paragraph 3426, for the values' listed in the December 6, 1988 submittal.
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Sincerely, P
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John F. Stang, Project Manager y.'
Project Directorate III-1 N
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- i IV, V & Special_ Projects OfficeofNuclearReactorkegulation 1
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- B. Ralph Sylvia _
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Detroit Edison Company CC Mr. Ronald C. Callen-Ms. Lynn Goodman Adv. Planning Review Section Supervisor - Licensing
, Michigan Public Service' Commission-Detroit Edison Company-6545 Mercantile'Way Fermi Unit 2 P.-0. Box 30221-6400 North Dixie Mighway.
Lansing, Michigan: 48909 Newport, Michigan 48166 John Flynn, Esq.
Senior Attorney Detroit Edison Company 2000 Second Avenue Detroit, Michigan. 48226
. Nuclear. Facilities and-Environmental 6
. Monitoring Section Office Division of Radiological Health P. 0. Box 30035 Lansing, Michigan 48909 i
- Mr; Thomas Randazzo
.i Director, Regulatory Affairs
' Detroit Edison Company Fermi Unit 2 6400 North Dixie Highway Newport, Michigan.48166 Mr.' Walt Rogers U.S. Nuclear Regulatory Commission Resident Intpector's Office 6450 W.- Dixie: Highway -
Newport, Michigan 48166 Monroe County Office of Civil Preparedness ~
963 South Rabinville
- Monroe, Michigan 48161 Regional Administrator, Region III U.S. Nuclear Regulatory Commission
-799RooseveltRpad Glen Ellyn, Illinois 60137 h,?
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- on the facility.
Accordingly, relief is granted from the requirements of ASME Cude,Section XI,1980 Edition, Winter 1981 Addendum, Subsection IW, Article
'iW-3000, Paragraph 3426, for the values listed in the December 6,1988 submittal.
Sincerely,
}ohn F. Stan, Project Mana
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Project Directorate III-1 Division of Reactor Projects - III,
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IV, V & Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page i
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