ML20036B363
| ML20036B363 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/10/1993 |
| From: | Colburn T Office of Nuclear Reactor Regulation |
| To: | Gipson D DETROIT EDISON CO. |
| Shared Package | |
| ML20036B364 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, TAC-M59620, NUDOCS 9305190263 | |
| Download: ML20036B363 (3) | |
Text
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.)J.i[j NUCLEAR REGULATORY COMMISSION
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j WASHINGTON, D.C. 20566 4001 e
May 10, 1993 1
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l Docket No. 50-341 i
Mr. Douglas R. Gipson Senior Vice President Nuclear Generation Detroit Edison Company 6400 North Dixie Highway i
I Newport, Michigan 48166 i
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Dear Mr. Gipson:
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SUBJECT:
REGULATORY GUIDE 1.97 - BOILING WATER REACTOR NEUTRON FLUX MONITORING - MPA A-17 TAC NO. M59620 i
i Section 6.2 of Generic Letter 82-33 requests applicants and licensees to l
provide a report on their implementation of Regulatory Guide (R.G.) 1.97, i
Revision 2, and methods for complying with the Conmission's regulations including supporting technical justification of any proposed deviations or i
alternatives. A large number of deviati'an requests were received from Boiling i
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 NEDD-31558, l
" Position on NRC Regulatory Guide 1.97, Revision 3,-Requirements for Post-Accident Neutron Monitoring System." The NED0 report proposes alternate l
criteria for neutron flux monitoring instrumentation in lieu of the Category 1 l
criteria stated in R.G. 1.97.
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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 (enclosed). The safety evaluation concluded that, for current BWR operating j
license and construction' permit holders, the criteria of NED0-31558 are j
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 1 i
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.
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Instrumentation to monitor the progression of core melt accidents is best i
addressed by the current severe accident management program.
You are requested to review your neutron flux monitoring instrumentation i
against the criteria of NEDO-31558 to determine whether you meet these
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criteria, and provide a letter to the NRC documenting the results of your j
review.
If you do not meet the criteria, you should either make a commitment t
to meet the criteria and state when this commitment will be fulfilled, or explicitly state any deviations from the criteria and provide supporting i
justification.
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9305190263 930510 i
PDR ADDCK 0500C341
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Mr. Douglas R. Gipson May 10, 1993 The criteria 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 should 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 1 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) 504-1341.
This request for information was approved by the Office of Management and Budget under clearance number 3150-0011 which expires June 30, 1994. Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, D. C. 20503.
Sincerely, Original signed by Timothy G. Colburn, Sr. Project Manager Project Directorate III-l Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page DISTRIBUTION:
C Docket: File ~
NRC & Local PDRs PD3-1 Reading File JRoe JZwolinski LMarsh MShuttleworth TColburn AHansen OGC BMarcus ACRS (10)
WShafer, RIII cc: Plant Service list 0FFICE LA:PDIII-l PM:PDIII-l LPM:RG1.97 PD:PDIII-In NAME MShuttle'w$ k TColburn F AHans h h f,L.Marshl E 2[/93 hp/93 f/ 7 /93 I @/93 DATE
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Mr. Douglas R. Gipson fe rmi-2 Detroit Edison Company cc:
John Flynn, Esquire Senior Attorney Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. O. Box 30195 Lansing, Michigan 48909 Mr. Wayne Kropp U.S. Nuclear Regulatory Commission Resident Inspector Office 6450 W. Dixie Highway Newport, Michigan 48166 Monroe County Office of Civil Preparedness 963 South Raisinville Monroe, Michigan 48161 Regional Administrator, Region III l
U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. William E. Miller
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Director - Nuclear Licensing Detroit Edison Company Fe rmi-2 6400 North Dixie Highway Newport, Michigan 48166 i
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