ML20154B046
| ML20154B046 | |
| Person / Time | |
|---|---|
| Issue date: | 09/06/1988 |
| From: | Liza Cunningham Office of Nuclear Reactor Regulation |
| To: | Grace D BWR OWNERS GROUP |
| References | |
| NUDOCS 8809130190 | |
| Download: ML20154B046 (3) | |
Text
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l SEP 0 01983 i
Mr. Donald Grac.e. Chairman l
BWR Owner's Group GPU Nuclear I Upper Pond Road Building E Parsipanny, New Jersey 07054 r
Dear Mr. Grace-
SUBJECT:
RESOLUTION OF OUTSTANDING ISSUES RELATIVE TO TOPICAL REPORT NEDO-31400 "SAFETY EVALUATION FOR ELIMINATING THE BOILING WATER REACTOR MAIN STEAM LINE ISOLATION VALVE CLOSURE FUNCTION AND SCRAM FUNCTION OF THE MAIN STEAM LINE RADIATION MONITOR" i
This letter is a followup to the meeting of August 15, 1988 between the BWR's Owner's Group and the USNRC on the above referenced topical report. We believe i
that the meeting was extremely useful, with each group developing a better l
understanding of the other's point of view.
l Following the meeting it was concluded by the USNRC staff that, in order to r
complete the staff review of the subject topical report, the following addi-tional information is needed:
1.
Describe alternatives to the removal of reactor scram and main steam i
line isolation valve (MSLIV) isolation functions from the steam line radiation monitors which could be utilized to overcome the N-16 spiking problem and why they were dismissed in favor of the function removal.
2.
Describe the emergency operations procedure (EOP) which would be
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utilized by the operators in lieu of the present steam line radiation monitorfunctionswhichwouldguideoperatoractionincaseofmajor fuel failure or a controi rod drop accident (CRDA).
3.
If steam line radiation monitor reactor scram and MSLIV isolation functions are removed, describe, in case of a CRDA, the modes for reactor scram and timing of the scram as compared with the present
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Donald Grace SEP 0 01988 4.
Describe the capability of augmented offgas (A0G) systems to handle the environment (e.g., radiation levels, hydrogen-oxygen gases) resulting from a CRDA.
Describe the E0P for the operation of the A0G system in the event of a CRDA.
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1 LeMoine J. Cunningham, Chief Radiation Protection Branch Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation cc:
JFulton, BWROG Distribution:
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- RfB:0 REP 15pickler FC5kopec 00 Lynch JEWigginton L4Cunningham 03/31/88 08/M/83 03/01/88 09/01/88
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Donald Grace 4.
Describe the capability of A0G systems to handle the environment (e.g., radiation levels, hydrogen-oxygen gases) resulting from a CRDA.
Describe the E0P for the operation of the A0G system in the event of a CRDA.
LeMoine J. Cunningham, Chief Radiation Protection Branch Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation cc:
JFulton, BWROG Distribution:
FJCongel, NRR LJCunningham, NRR 00 Lynch, NRR JEWigginton, NP.R 15pickler, NRR FC5kopec, NRR TECollins, NRR W0 Travers, NRR RJBarrett, NRR Central Files RPBR/F3 l
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