ML19338F811
| ML19338F811 | |
| Person / Time | |
|---|---|
| Issue date: | 10/15/1980 |
| From: | Arlotto G NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | Fraley R Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML19338F812 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097, TASK-OS, TASK-RS-917-4 NUDOCS 8010270323 | |
| Download: ML19338F811 (2) | |
Text
. _ _ _ _
L.,
i y
s UNITED STATES Hog %
NUCLEAR REGULATORY COMMtsslON f{T, g-(j WASWNCTCN, D. C. 20555 S. M /s/
ocT n isgo s.,
MEMORANDCM FOR: Raymond F. Fraley, Executive Director Advisory Cemittee on Reactor Safeguards FROM:
Guy A. Arlotto, Director Division of Engineering Standards Office of Standards Development
SUBJECT:
ORAFT 3 0F REVISION 2 TO REGULATORY GUIDE 1.97,
" INSTRUMENTATION FOR LIGHT-WATER-COOLED NUCLEAR POWER PLANTS TO ASSESS PLANT AND ENVIRONS CONDITIONS OURING AND FOLLOWING AN ACCIDENT" Enclosed for the use of the ACRS Regulatory Activities Subcommittee are fifteen (15) copies of Draft 3 of Revision 2 to Regulatory Guide 1.97, "Instrumentaticn for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident", dated October 8, 1980. Also enclosed are fifteen (15) copies of the Value-Impact Statement attached to the guides.
Oraft 2 of Revision 2 to Regulatory Guide 1.97, was reviewed by the ACRS Regulatory Activities Subcomittee on August 6,1980 and by the full ACRS on August 7, 1980. The guide was referred back to the staff to consider the ACRS concerns which were outlined in Chainnan Plesset's letter dated August 13, 1980. The following changes to the guide have been made to address these concerns:
(1) The guide has been modified to eliminate the necessity for many of the footnotes and cross-references which should make the guide more clear.
(2) The scope of the guide has been reduced to address only instrumenta-tion required by the control room operating personnel. The relationship of the guide to the emergency response facilities will be included in the criteria for those facilities and not in this rogulatory guide.
(3) The six different design and qualification criteria categories have been consolidated into three categories, which will reduce the complexity.
In addition to the above changes, the NRC staff has met with the ANS-4.5 Work-ing Group in an attempt to resolve some of the major differences which existed.
The folicwing changes to the guide were made as a result of this effort:
1 80102703%3,
gpg g
~
e
-o.
OCT 151c80 To:
R. F. Fraley
-2 (1) Development of Type D and E variable lists as part of ANS-4.5 was deleted.
Types D and E variable lists are developed independent of the ANS standard.
(2) The guide was mcdified to make it clear that advanced technology in developing accident monitoring infomation may be used.
(3) Adjustments were made to the variable lists which added some variables deemed important by the ANS personnel and the NRC staff, and deleted some which were only considered desirable.
Regarding the core exit thermoccuples in BWRs, it is believed by some members of the staff that a diverse measurement to coolant level in the reactor is essential in detemining the accomplishment of the function of core cooling.
Hence, the measurement of core exit temperature is still in the list. The staff is continuing to study the problem and justification of this position will be presented at the ACRS meeting.
The staff believes that the ACRS concerns expressed in Dr. Plesset's letter have been adequately addressed and requests ACRS concurrence in the Regulatory Position of Draft 3.
VY Guy A. Arlotto, Director Division of Engineering Standards Office of Standards Development
Enclosure:
as stated PugeDocumentRoch cc:
I I
)
i
_