ML20207F087
| ML20207F087 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek, LaSalle, 05000000 |
| Issue date: | 12/19/1986 |
| From: | Bournia A Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20207F049 | List: |
| References | |
| NUDOCS 8701050431 | |
| Download: ML20207F087 (3) | |
Text
pa December 19, 1986
)
Docket Nos: 50-373 DISTRIBUTION:
and 50-374 S N 373/374 %"
NRC PDR Local PDR Mr. Dennis L. Farrar BWD-3 r/f Director of Nuclear Licensing EAdensam Comonwealth Edison Company EHylton P.O. Box 767 ABournia Chicago, Illinois 60690
_RBernero Attorney, OGC
Dear Mr. Farrar:
JPartlow EJordan
Subject:
10 CFR 50.62, ATWS Rule BGrimes ACRS(10)
In accordance with 10 CFR 50.62(c)(6), licensees and applicants for boiling 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.
As a participant in the BWR owners group topical report, you may reference the topical report 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 checklist (in Appendix A of the staff's SER) to address your design requirements. For the PPT System, you should indicate whether your installed system is the same as the Monticello design or the modified Hatch design. The staff requires those utilities with other RPT designs to submit their schedule to upgrade their designs to either of the above approved designs or to demonstrate that their present design can perfom its function in a reliable manner eauivalent to the two approved designs.
In order to complete the review of compliance with 10 CFR 50.62 for la Salle County Station, Units 1 and 2, it is requested that you submit information as discussed above within 90 days of receipt of this letter.
hNb 4
P
Mr. Dennis L. Farrar la Salle County Nuclear Power Station Commonwealth Edison Company
. Units 1 & 2 CC*
Philip P. Steptoe, Esquire John W. McCaffrey Suite 4200 Chief, Public Utilities Division One First National Plaza 160 North La Salle Street, Room 900 Chicago, Illinois 60603-Chicago, Illinois 60601 Assistant Attorney General 188 West Randolph Street Suite 2315 Chicago, Illinois 60601 Resident Inspector /LaSalle, NPS U.S. Nuclear Regulatory Commission Rural Route No. 1 P. O. Box 224 Marseilles, Illinois 61341 Chairman la Salle County Board of Supervisors La Salle County Courthouse Ottawa, Illinois 61350 Attorney General 500 South 2nd Street Springfield, Illinois 62701 Chairman Illinois Commerce Commission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 Mr. Gary N. Wright, Manager Nuclear Facility Safety Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Rossevelt Road Glen Ellyn, Illinois 60137
~-... This reouest for information was approved by OMB under clearance number 3150-0011.
Sincerely, Anthony Bournia, Pro.iect Manager BWR Project Directorate No. 3 Division of RWR Licensing
Enclosure:
Safety Evaluation (AN0:8611030127) cc w/ enclosure:
See next page cD BWD-3: DBL BWI), 3BL D
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