ML19351A352
| ML19351A352 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/10/1989 |
| From: | Stang J Office of Nuclear Reactor Regulation |
| To: | Sylvia B DETROIT EDISON CO. |
| Shared Package | |
| ML19351A353 | List: |
| References | |
| TAC-59094, NUDOCS 8910200108 | |
| Download: ML19351A352 (4) | |
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mTEOsTATE8 NLA:LCAR REGULATORY COMMISSION waammevow, p. c. sones l
October 10~, 1989 Docket No. 50-341 Mr. B. Ralph Sylvia Senior Vice President Nuclear Operations Detroit Edison Company 1
6400 North Dixie Highway Newport, Michigan 48166
Dear Mr. Sylvf a:
SUBJECT:
FERMI-2 COMPLIANCE WITH THE ATWS RULE, 10 CFR 50.62 (TAC N0. 59094) l By letter dated December 19, 1986, the NRC requested Detroit Edison Company (Deco)
- o provide a schedule when Deco intended to submit information sufficient to l
. demonstrate to the NRC the adequacy of the ATVS mitigation features at Fermi-2 in satisfying the requirements of 10 CFR 50.62.
By letter dated February 27, 1987, Deco responded to the December 19, 1906, request. The response indicated l
that an Alternate Rod Insertion (ARI) system had been installed and was i
operational and the system description was in the Updated Final Safety Analysis l
(UFSAR).
The response also indicated a Recircu'istion Pump Trip (RTP) had been installed and made operational and the system description was containei in the UFSAR.
In addition the response.a,1so described, t.he modifications to uu: Standby e'
Liquid Control System (SLCS) to' meet the ' requirements of 10 CFR 50.67.
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- -33. t The staff reviewed the information contained in the DECc February 21, 1967, letter and the UFSAR concerning ATWS mitigation features at Forzi-2 and concluded that the information provided by DECO was not sufficient for the staff to determine compliance with 10 CFR 50.62.
By letter dated March 31, 1988, the NRC l
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requested Deco to respond to questions concerning specific designs of the ARI and the RTP at Fermi-2.
By letter dated April 20, 1988, Deco provided responses to the request for additional information.
Following inspectione and meetings with Deco late in 1988, the staff identified five areas of concern that the Fermi-2 design was not in full compliance with the ATWS Rule.
These concerns were diversity, testability, manual initiation, conoletion of protective action once initiated, and the information available to the operator.
By letter dated June 15, 1989, Deco submitted revised design information whi:h addressed all the above concorr.s.
The staff has reviewed the new informatici.
Based n the enclosed SE, the staff finds the Fermi-2 design of the ATWS mitiga, ion features with the exception of diversity are in compliance with '.he
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requirements of 10 CFR 50.62.
The subject of diversity will be hendled on ~a generic basis and information concerning this will be coming to you under a i
separate cover, i
By letter dated May 11, 1989, DECO requested a change to their Technical Specifications to reflect the use of sodium pentaborate enriched with the Boron-10 isotope to meet the requirements of the ATWS rule, 10 CFR 50.62 paragraph C(4) concerning the Standby Liquid Control System.
By letter dated September 1, 1989, 8910200108 891010 h
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DR ADOCK 0500 41 i
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7 Mr. 8. Ralph Sylvia ;
the NRC issuert Amendment No. 38 to facility Operating License No. NPF-43 for the i
Fermi-2 facility which approved the modifications by DECO to meet the requirements of 10 CFR 50,.62 paragraph,C(4).
l By. letter dated March 17, 1989,~ Deco committed to install all ATWS mitigation I
features to meet 'the' requirements of 10 CFR 50.62 during the first refueling r.
outage which starts ~on. September 4, 1989.
The staff finds the installation schedule acceptable.
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This completes the' staff's evaltiation of the Fermi-2 ATWS mitigation features l
compliance with 10 CFR 50.62 with the exception of diversity which will be 1
examined penerically.as indicated above.
The staff considers TAC No. 59094 i
closed.
t Sincerely, i
OriginalsirM by I
John F. Stang, Project Manager.
l Project Directorate III-1 Division of P.eactor Projects - III, IV, V & Special Projects i
Office of Nuclear Reactor Regulation
Enclosure:
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.As stated cc w/ enclosure:
See next page i
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Mr. 8. Ralph Sylvia.
the NRC issued Amendment No. 38 to Facility Operating License No. NPF-43 for the Fermi-2 facility which approved the modifications by Deco to meet the requirements of 10 CFR 50.62 paragraph C(4).
By letter dated March 17, 1989, Deco committed to install all ATWS mitigation features to meet the requirements of 10 CFR 50.62 ouring the first refueling outage which starts on September 4, 1989.
The staff finds the installation schedule acceptable.
This completes the staff's evaluation of the Fermi-2 ATWS mitigation features compliance with 10 CFR 50.62 with the exception of diversity which will be examined generically as indicated above.
The staff considers TAC No. 59094 closed.
Sincerely, k
t K' J6hn F. Stan Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects i
Office of Nuclear Reactor Regulation
Enclosure:
As stated
- .J, cc w/ enclosure:
See next page 4
Mr. B. Ralph Sylvia Femi-2 Facility Group Vice President - Nuclear Operations Detroit Edison Company 6400 North Dixie Highway Newport, Michigan 48166 Mr. Ronald C. Callen Ms. Lynn Goodman Adv. Planning Review Section Supervisor - Licensing Michigan Public Service Cosmicsion Detroit Edison Company 6545 Mercantile Way Fermi Unit 2 P. C. Box 20221 6400 North Dixie Highway Lansing, Michigan 48909 Newport, Michigan 48166 John Flynn, Esq.
Senior Attorney Detroit Edison Compsny 2000 Seccnd Avenue Detroit, Michigan 48226 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health P. O. Box 30035 Lansing, Michigan 48909 Mr. Thomas Randazzo Director, Regulatory Affairs Detroit idison Company Fermi l;. sit 2 6400 North Dixie Highway Newport, Michigan 48166
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Mr. Walt Rogers U.S. Nuclear Regulatory Commission Resident Inspector's Office 6450 W. Dixio Highway Newport, Michigan 48166 Monroe County Office of Civil Preparedness 963 South Raisinville Monroe, Michigan 48161 l
Regional Administrator, Region III l
U.S. Nuclear Regulatory Commission i
799 Roosevalt Road Glen Ellyn, Illinois 60137 1
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