ML17252A755
| ML17252A755 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, LaSalle  |
| Issue date: | 06/03/1993 |
| From: | Chandu Patel Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML17252A756 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-M77660, NUDOCS 9306100320 | |
| Download: ML17252A755 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. O.C. 20566-0001 Docket Nos. 50-237, 50-249 50-373, 50-374 and 50-254, 50-265 Mr. D. L. Farrar Manager, Nuclear Regulatory Services Co111T1onwealth Edison Company Executive Towers West Ill, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515
Dear Mr. Farrar:
June 3, 1993 Enclosure
SUBJECT:
REGULATORY GUIDE l.97 - BOILING WATER REACTOR NEUTRON FLUX MONITORING (TAC NO. M77660)
Section 6.2 of Generic Letter 82-33 requests applicants and licensees to provide a report on their implementation of Regulatory Guide (R.G.) 1.97.
Revision 2, and methods for complying with the Commission's regulations including supporting technical justification of any proposed deviations or alternatives. A large number of deviation requests were received from Boiling Water Reactor (BWR) applicants and licensees concerning neutron flux monitoring instrumentation.
These requests were initially denied.
In support of these requests, the BWR Owners' Group submitted NED0-31558, "Position on NRC Regulatory Guide 1.97, Revision 3, Requirements for Post-Accident Neutron Monitoring System."
NED0-31558 proposes alternate criteria for neutron flux monitoring instrumentation in lieu of the Category 1 criteria stated in R.G. 1.97.
The staff has completed its evaluation of NED0-31558, and by letter dated January 13. 1993, to the BWR Owners' Group, issued a safety evaluation (SE)
(enclosed).
The SE concluded that, for current BWR operating license and construction permit holders, the criteria of NED0-31558 are acceptable.
However, for new license applications for both conventional and advanced BWR designs, the R.G. 1.97 criteria must be met for neutron flux monitoring instrumentation.
The staff further concluded that Category l neutron flux monitoring instrumentation is not needed for existing BWRs to cope with a Loss-of-Coolant Accident, Anticipated Transient Without Scram; or other accidents that do not result in severe core damage conditions.
Instrumenta-tion to monitor the progression of core melt accidents is best addressed by the current severe accident management program.
You are requested to review your neutron flux monitoring instrumentation against the criteria of NED0-31558 to determine whether you meet these criteria, and provide a letter to the NRC documenting the results of your review.
If you do not meet the criteria, you should either make a commitment to meet the criteria and state when this commitment will be fulfilled, or
Mr. D. June 3, 1993 explicitly state any deviations from the criteria and provide supporting justification.
The criteri~ of NED0-31558 include the use of uninterruptible and reliable power sources.
The BWR Owners' Group and the staff agree that redundant neutron flux monitoring channels should be powered from different uninterruptible power supplies (UPS), so that loss of a single UPS would not cause the loss of all channels.
You are, therefore, requested to perform a plant-specific evaluation to review the power supplies to neutron flux monitoring instrumentation, including recorders.
This review should verify that power would not be lost during design basis events by load shedding logics or similar schemes, and that a single power supply failure would not cause the loss of all channels.
The results of this review ~hould be indicated in your response to the staff concerning this issue.
Since neutron flux monitoring instrumentation for BWRs is no longer considered to be Category l instrumentation, you may request the removal of neutron flux monitoring instrumentation from your post-accident monitoring technical specifications.
If you wish to maintain a post-accident monitoring technical specification on this instrumentation, you may do so.
Please notify the NRC, within 60 days of receipt of this letter, of the actions you plan to take and your schedule for implementation.
If you have any questions regarding this issue, please do not hesitate to contact me at (301) 504-3025.
This request for information was approved by the Office of Management Budget under clearance number 3150-0011 which expires June 30, 1994.
on burden and duplication may be directed to the Office of Management Budget, Reports Management Room 3208, New Executive Office Building, Washington, D. C. 20503.
Sincerely,
~Pf~
Chandu P. Patel, Project Manager Project Directorate III-2 and Comments and Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc:
See next page
Mr. D. L. Farrar Commonwealth Edison Company cc:
Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. C. Schroeder Plant Manager Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 U. S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station 6500 North Dresden Road Morris, Illinois 60450-9766 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Robert Neumann Office of Public Counsel State of Illinois Center 100 W. Randolph Suite 11-300 Chicago, Illinois 60601 Dresden Nuclear Power Station Unit Nos. 2 and 3
Mr. D. L. Farrar Commonwealth Edison Company cc:
Phillip P. Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Assistant Attorney General 100 West Randolph Street Suite 12 Chicago, Illinois 60601 Resident Inspector/LaSalle, NPS U. S. Nuclear Regulatory Commission Rural Route No. 1 P. 0. Box 224 Marseilles, Illinois 61341 Chairman LaSalle County Board of Supervisors LaSalle 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 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Robert Neuman Office of Public Counsel State of Illinois Center 100 W. Randolph Suite 11-300 Chicago, Illinois 60601 LaSalle County Station Unit Nos. 1 and 2 Robert Cushing Chief, Public Utilities Division Illinois Attorney General's Office 100 West Randolph Street Chicago, Illinois 60601 Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. G. Diederich LaSalle Station Manager LaSalle County Station Rural Route 1 P. 0. Box 220 Marseilles, Illinois 61341
Mr. D. L. Farrar Commonwealth Edison Company cc:
Mr. Stephen E. Shelton Vice President Iowa-Illinois Gas and Electric Company P. 0. Box 4350 Davenport, Iowa 52808 Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. Richard Bax Station Manager Quad Cities Nuclear Power Station 22710 206th Avenue North Cordova, Illinois 61242 Resident Inspector U. S. Nuclear Regulatory Commission 22712 206th Avenue North Cordova, Illinois 61242 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, Illinois 61201 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Robert Neumann Office of Public Counsel State of Illinois Center 100 W. Randolph Suite 11-300 Chicago, Illinois 60601 Quad Cities Nuclear Power Station Unit Nos. 1 and 2