ML19254F868
| ML19254F868 | |
| Person / Time | |
|---|---|
| Issue date: | 11/06/1979 |
| From: | Hintze A NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | NRC OFFICE OF THE SECRETARY (SECY) |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097, TASK-OS, TASK-RS-917-4 NUDOCS 7911190299 | |
| Download: ML19254F868 (1) | |
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Please olace the attached docu ent in the POR usir.g the following file and file points -
POR File Additicnal Info (Select one ano enter number)
(Enter if appropriate)
Proposed Rule (PR)
ACRS Minutes fio.
Reo. Guide /. 9 7 R,wsym A Relctes to Propcsed Rule (PR)
Petition (PR.1)
Relates to Reg. Guide /.f7 f
Effective Rule (R':)
AilSI Relates to Petition (PRM)
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Instrumentation is also needed to provide information about some plant parar..eters that will alert the operator to conditions that have degraded beyond those postulated in the accident analysis.
In particular, it is important that the coerator be informed recarding that status of coolant level in the reactor vessel or the existence of core voidina which would indicate degraded core coolina.
Direct indication of coolant level in the reactor vessel is not currently available in oressurized water reactors.
However it is imoarative that this capability be develooed within a reasonable time in order to provide the coerator with this vital information in a cositive, unambicuous manner.
It is essential that degraded conditions be identified so that the operator can take actior.
that are available to mitigate the consequences.
It is not intended that the operator be encouraged to circumvent systems important to safety prematurely, but that he be adequately infonned in order that unplanned actions can be taken when necessary.
Additions to TABLE 3 - BWR VARIABLES Measured Variable Range Type Puroose CORE:
Core Exit Temperature 150*F to 2300*F B,C ANS-4.5, Section 6.2.3 Provide incore temperature measurements to identify localized hot areas.
(Approximately 50 ceasure=ents)
POST-ACCIDENT SAMPLING CAPABILITY:
A Provide means for saf e and convenient Upstream of the S'andby As required based on sampling.
These previsions should Cas Treat =ent System for Reg Guide 1.3 guide ~
- 1 Each Area Served lines h 1 ding to.=aintain radiation deses ALAPA,
- 2. sa ple containers with cestainer-sa.pling port connector cocpatibili
- 3. capability of saspling under primary system pressure and negative pressur
- 4. handling and transport capability, a
- 5. pre-arrange =ent for analysis and interpretation.
CONTAINMENT:
Containment and Drywell O to 10ll 3,C For indication of the'need for, and a Oxygen Concentration (capability of operat-
=easurement of the perfor=ance of the (for these plants with ing f rom 12 psia to contain=ent oxygen elimination system.
2 inerted containments) design pressure
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