ML17199F977
| ML17199F977 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/17/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| References | |
| TAC-59089, TAC-59090, NUDOCS 8701140047 | |
| Download: ML17199F977 (2) | |
Text
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- 'i' December@, 1986
- Docket.Nos. 50-237/249 Mr. Dennis L. Farrar Director of Nuclear-Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Farrar:
C Dj_s.t.r..iJ1u.tio.n w/encl osures Docket Fi 1 e I
.. JS tang NRC-PDR CJamerson Local PDR Dresden File BWDl Reading
SUBJECT:
PLANT-SPECIFIC ATWS REVIEW GUIDELINES AND IMPLEMENTATION SCHEDULE (MPA A-20 AND TAC 59089 and 59090)
Re:
Dresden Nuclear Power Station, Unit Nos~ 2 and 3.
Enclosed is the staff's October 21,.1986, safety ev~luation (SE) in support of the BWR Owners Group's licensing topical response to the ATWS rule, 10 CFR 50.62.
In accordance ~ith paragraph (c)(6) of 10 CFR 50.62, you are required 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 pump trip (RPT) system.
Those. licensees who particip~ted in.the BWR Owners Group topical report may reference the topical report in support of their plant-specific submittal.
For the SLC system, you should choose one of three alternatives and follow the.
condition stated in the staff's SE.
For the ARI system, we suggest you use the checklist found in Appendix A of the staff's SE to address the design
- details and its conformance with the ARI design objectives and design basis requirements.
For the RPT system, you should indicate whe_ther your installed system is the same as the Monticello design or the modifi~d Hatch design. The*
staff requires those utilities with the RPT designs to submit theit_schedule to upgrade their designs to either of, the above approved designs or to demonstrate that their present design can perform its function in a*reli~ble manner equivalent to the two approved d~si~ns., _
Technical Specifications should be proposed.for ATWS r~l~t~d com~orienil in your plant-specific submittal.
In order to support timely c-lo"sure of' this issue we request plant-specific inputs by ~~.rch 3_1, 1987.
Please a_dvise John*
Stang, your NRC Project Manager, of any problems or questions.
This request for information was approved ~Y OMB under clearance numb~r 3150-0011.
8701140047 861217. : (**\\. ~
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Enclosure:
Safety Evaluation (AN0:8611030127) cc w/enclosure:
See next page OFC
- DLB:BWDl
- DBL:BWD
,*$incerely;_*'
Original;_*signed by John.A. Zwolinski, Director BWR_ Project Directorate #1 DiVision of BWR Licensing Distribution w/o enclosure RBernero EJordan EMarinos*
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NAME :CJamerso
- JZwolinski DATE : 12N\\ /86
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Mr. Denf'liS L. Farrar Commonwealth Edison Company cc:
Mr. Michae1 !. Miller Isham, Lincoln ~ Beale Three First National Plaza Suite 5200 Chicago, Illinois 60602
~r. J. Eenigenburg Plant Superintendent Dresdef'I ~'uclear Power Station Rural Route #1 Morris, Illinois 60450 U. S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station Rural Route #1 Morris, Illinois* 60450 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Regional Administrator Dresden Nuclear Power Station.
Units 2 and 3.
Nuclear Regulatory Cormnission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Michael E. Parker, Chief Divisfon of Engineering Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th ~loor Springfield, Illinois 62704