ML20207F121
| ML20207F121 | |
| Person / Time | |
|---|---|
| Site: | Fermi, Hope Creek, 05000000 |
| Issue date: | 12/19/1986 |
| From: | Stefano J Office of Nuclear Reactor Regulation |
| To: | Sylvia B DETROIT EDISON CO. |
| Shared Package | |
| ML20207F049 | List: |
| References | |
| NUDOCS 8701050454 | |
| Download: ML20207F121 (3) | |
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December _19,1986 Docket No. 50-341-Mr. B. Ralph Sylvia NRC PDR Attorney, OGC Group Vice President - Nuclear Operations Local PDR ACRS (10)
Detroit-Edison Company BWD-3 r/f JPartlow 6400 North Dixie Highway EAdensam EJordan Newport, Michigan 48166:
EHylton BGrimes RBernero Glainas
Dear Mr. Sylvia:
JStefano MWPodges
Subject:
Fermi-2 Compliance with the ATWS Pule, 10 CFR 50.62 Inaccordancewith10CFR50.62(c)(6),licenseesandapplicantsforboiling water reactor (BWR) nuclear power plants are reouired to submit sufficient information to demonstrate to the Commission the adequacy of an alternate rod injection (ARI) system, a standby liquid control (SLC) system and a reliable reactor coolant recirculating pumps trip (RPT) system.
The staff has completed its review of licensing topical report NEDE-31096-P,
" Anticipated Transients Without Scram; Response to NRC ATWS Rule,10 CFR 50.62",
submitted by the BWR Owner's Group. NEDE-31096-P details conceptual designs to satisfy the 10 CFR 50.62 requirements for boiling water reactors. The staff's safety evaluation of that report is enclosed for your information.
Since Detroit Edison participated in the BWR owners group topical report you may reference the topical in support of your plant specific submittal'. For the SLC system you should choose one of the three alternatives and follow the conditions stated in the staff's SER. For the ARI system, you may use the check list (in Appendix A of the SER) to address your design requirements. For the RPT system, you should indicate whether your installed system is the same as the Monticello design or the modified Hatch design.
If you have other designs, you are required to submit a schedule to upgrade them to either of the above approved designs or to demonstrate that your present design can perfom its function in a reliabic manner equivalent to the two approved designs.
To the extent that the ATWS mitigation features at Fermi-2 do not conform to those in the topical, or for unique desion changes made at Femi-2 to satisfy the requirements of 10 CFR 50.62, you must provide information in accordance l
with 10 CFR 50.62(c)(6).
Deco letter to the NRC dated October 12,1985,(VP-85-0200) provided an imple-mentation schedule which indicated that Fermi-2 will be in full compliance with the requirements of 10 CFR 50.62 before startup followine the second refueling outage.
It was further noted in that letter that Fermi-2 has an Alternate Rod Insertion (ARI) system and a Recirculation Pump Trip (RPT), both of which are installed and operational, and that modifications to the Standby Liquid Control System (StCS) will be completed in order to meet the requirements of 50.62(c)(4)
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-before startup following the second refueling outape.
Within 60 days after receipt of this letter, please provide your schedule as to I
- FoR29MM8n8lk P
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Mr. B. Ralph Sylvia Detroit Edison Company Fermi-2 Facility cc:
Mr. Harry H. Voigt, Esq.
Ronald C. Callen LeBoeuf, Lamb, Leiby & MacRae Adv. Planning Review Section 1333 New Ha:npshire Avenue, N. W.
Michigan Public Service Comission Washington, D.'C. 20036 6545 Mercantile Way P. O. Box 30221 John Flynn, Esq.
Lansing, Michigan 48909 Senior Attorney Detroit Edison Company Regional Administrator, Region III 2000 Second Avenue
- 11. S. Nuclear Regulatory Comission Detroit, Michigan 48226 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Dennis R. Hahn, Chief Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health P. O. Box 30035 Lansing, Michigan 48909 Mr. Robert Woolley Acti19 Supervisor-Licensing Detroit Edison Company Fermi (Init 2 6400 North Dixie Highway Newport, Michigan 48166 Mr. Walt Rogers U. S. Nuclear Regulatory Commission Resident Inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 Monroe County Office of Civil Preparedness 963 South Raisinville Monroe, Michigan 48161
. when DECO intends to submit information sufficient to demonstrate to the Com-mission the adequacy of the ATWS mitigation features at Fermi-2 in satisfying the requirements of 10 CFR 50.62. Your schedule should make allowances for the NRC staff's review and approval of those submittals, including time for possible additional information that the staff may request, or modifications that may be found to be necessary, so as not to impact the Fermi-2 second refueling outage schedule.
If there are any questions concerning this letter, please contact me at 301-492-9473.
This request for information was approved by OMB under clearance number 3150-0011.
Sincerely, John J. Stefano, Sr., Pro.iect Manager BWR Prcject Directorate No. 3 Division of BWR Licensing
Enclosure:
As stated Safety Evaluation (AN0:8611030127) cc: w/ enclosure See next page S
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