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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\...../ SEP 0 01983 l
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 [
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 mode,
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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.
On . a; ; . '
U h Q l.I . f . ! ' : 1 LeMoine J. Cunningham, Chief Radiation Protection Branch Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation cc: JFulton, BWROG Distribution:
i FJCongel, NRR LJCun'.ingham, NRR ,
00Lych, NRR JEWigginton, NRR 15pickler, NRR FC5kopec, NRR TECollins, NRR WDTravers, NRR RJBarrett, NRR POR Central files RPB R/F P
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- 5ee previous .oncurrence
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- f. 09/06/88
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
RF P RPS: 0 REP dq- [2 REP { PB:0 REP C:RPB:0 REP I i er FJ6Cohc LJCunningham OL%ylich {&JEWigginton
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