ML20151B773
| ML20151B773 | |
| Person / Time | |
|---|---|
| Issue date: | 01/23/1981 |
| From: | Arlotto G NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | Fraley R Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML19350B681 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097, TASK-OS, TASK-RS-917-4 ACRS-R-0924, ACRS-R-924, NUDOCS 8102180822 | |
| Download: ML20151B773 (3) | |
Text
_ -- - - - - - - . .- . . - . - . .- ,
t' h ? h g 2 3 1981 MEMORANDUM FOR: Raymond Fraley, Executive Director Advisory Committee on Reactor Safeguards FROM: Guy A. Arlotto. Director Division of. Engineering Standards Office of Standards Development StBJECT: REGULATORY GUIDE 1.97, " INSTRUMENTATION FOR LIGHT-WATER-COOLED NUCLEAR POWER PLANTS TO ASSESS PLANT AND ENVIRONS CONDITIONS DURING AND FOLLOWING AN ACCIDENT" Dr. Milton S. Plesset's letter to Mr. William J. Dircks dated November 10, 1980, gave the ACRS concurrence in. Modified Draft 3 of Revision 7. to Regulatory.
Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an accident," with some exceptions and comments. The following is in response to those comments.
- 1. Dr. Plesset commented that the ACRS concerns regarding potential usefulness of core themocouples in BWRs have been resolved to some extent and noted that the vertical location of these themocouples has not yet been decided but suggested that a location close to the top of the core may be desirable.
He also commented that further detailed consideration of how the infomation from these instruments will be used will be required before the optimum location can be detemined.
Response - The staff agrees with the ACRS that further consideration is necessary before the optima vertical location can be detemined. Therefore, the guide has been issued with no definitive location specified beyond the provision that there be four themocouples per quadrant.
- 2. Dr. Plesset commented that the requirements for installed instruments for radiation exposure rates in the environs of a plant are deficient and recommended that the requirements be deleted until suitable guidance can be provided.
Response - The staff agrees with this comment insofar as it pertains to the Type C eariable. Therefore, the variable has been deleted from the Type C list. The discussion with the ACRS concentrated on the use of this variable as a means of detecting releases from the containment from unidentified release points. Since the function of detectigg primary containment breach must still be performed, it will be accomplished by s)g monitoring the radiation exposure rates inside buildings such as the auxiliary building, the fuel handling building, the secondary containment, d,p\
etc., whose inside areas are in direct contact with the primary contaiment. '
It-is-beHeved-thet-tha highestrprobabMity-fee-e-breech-ef-the-peteery
- " c) . containment. will_be where penetrations. and hatches are located.
MDljYDY ' ' '
.n : .+2 .n n. " "
C. F= \ C l.- l. R E C C R D C C F= 1 '
To: R. F. Fral ey For completeness, however, the variable " Radiation Exposure Rake in th'e .
Environs" has been retained in the list of Type E variables (those variables to monitor release of radioactive materials) since measurement of the variable provides important inforsmation for the radiological energency response program as well as for the control room operator. Reference is made in the guide to MUREG-0654, " Criteria for Preparation and Evaluation
'of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" for the detailed requirements of the measurement.
The additional guidance suggested by the ACRS as being necessary for the installed instruments to measure this variable will be developed and evaluated by NRR as the program to meet the criteria of MUREG-0654 is implemented. Thus, the staff believes that it has been responsive to the ACRS comment.
- 3. Dr. Plesset commented that since the design of the instruments of Regulatory .
Guide 1.97 is closely linked to and may be influenced by their utilization in the Emergency Response Facilities, the requirements for these facilities should be decided upon and promulgated promptly or else the implementation schedule of Regulatory Guide 1.97 should be modified accordingly.
Response - The staff agrees with this casusent. It is the intent of the staff to issue MUREG-0696. " Functional Criteria for Emergency Response Facilities " within a few weeks. This will allow for the integration of the design of these facilities with the design cf the instrumentation provided by Regulatory Guide 1.97, thus, making it unnecessary to modify the implementation date as proposed in the-guide. , - ,
/ p- ' (,_ hp C( i n;' J l s G. A. Ar1 tto, Director Division of Engineering Standards Office of Standards Development bec: W. Dircks R. Smith T. Murley G. A. Arlotto W. M. Morrison E. C. Wenzinger D. F. Sullivan A. S. Hintze ntwmmn9 AL A D RSSB wr<
RSSB RD RSSB SUBJ. 6097 Tas k No . RS-917-4 BR8-17?t78i
- > SD:RSSB S f SD:GES .r Y. SD:0E
(;Q
'~o e o 0-
.ASHINTZE- ' ECWENZINGER . WMMORRISON - ,.GAA
l/A' /81 . IfM81 1/p/81 1/ N/81
- - 2 e .e ~. o gy;;: 2 ; : g . ,: ; .
. ::/ ~Z~
.o
- 3 "> -w s :s n 7 m j JAN 2 3 7931 :
To: R. F. Fraley 1 r For completeness, however, the variable " Radiation Exposure Rate in' the "
Environs
- has been retained in the list of Type E variables (those variables I to monitor release of radioactive saterials) since seessreent of the variable provides ' e%st infbreation for the radiological emergency response progree is sil as for the Control room operator. Reference is .,
i %sede in the guide co AGREG-0654, " Criteria for Preparation and Evaluation
- of Radiological Energency Response Plans and Preparedness in Support of i
Nuclear Power Plants
- for the detailed requirments of the measurement.
The additional guidance suggested by the ACR$ as being necessary for the installed instruments to measure this variable vill be developed and ,
i evaluated by MRR as the program to meet the criteria of NUREG-0654 is implemented. Thus, the staff believes that it has been responsive to the ,
1 ACR$ Comt.
r i
I 3. Dr. Plesset commented that since the design of the instruments of Regulatory Gaide 1.97 is closely linked to and may be influenced by.their utilization ;
in the Emergency Response Facilities, the requirments for these facilities
-' simuld be decided upon and promulgated promptly or else the implementation schedule of Regulatory Guide 1.97 should be modified accordingly.
Response - The staff agrees with this comment. It-is the intent of the , !
staff to issue NURES-0696, " Functional Criteria for Emergency Response i i Facilities," within a few weeks. This will allow for the integration of.the i. '
i design of these facilities with the design of the instrtamentation provided by Regulatory Guide 1.97, thus, making it unnecessary to modify the .
implementation date as proposed in t gu4de. . . -
\
/
) '
/ M. g G * ~!/ 8l"/y' .7#
~7 - .
G. A. Arl'o tto, Director l Division of Engineering Standards !
Office of Standards Development l
bec: W. Dircxs R. Smith T. Murley G. A. Arlotto ,
, , W. M. N rrison E. C. Wenzinger D. F. Sullivan i A. S. Hint:e DISTRIBUTION i CENTRAL FILE l 30 ALPHA SD RD ,
RSSB WR RSSB RD )
RSSB SUBJ. 5097 i
Tas k No . P.5-917 4
~3W17??73i f SD:RSSB S MfM3
'IAf@, '~~S D:GES# .*.f- 0- -- ""/t "M . S[D :
~" ~
ag_,,
- ... 814 TIE ~ . -4CWENZINGER
. WMMORRISON -# .
"h. . 11/M131 . l1(L.t 31 . ll.6/.81 . .
1Q/31 L .L . ...
'ECOR O C O?Y ": x-m -
sa: :== r s : n +:2 :" OFFICIA L
UNITED STATES I
[(pch Qtoog . ,o, g NUCLEAR REGULATORY COMMISSION l
,c . j r gg)/ . j WASWNGTON. O. C. 20555 kv /% .=
JAN 2 3 to81 MEMORANDUM FOR: Raymond Fraley, Executive Director Advisory Comittee on Reactor Safeguards FROM: Guy A. Arlotto, Director Division of Engineering Standards Office of Standards Development
SUBJECT:
REGULATORY GUIDE 1.97, " INSTRUMENTATION FOR LIGHT-WATER-COOLED NUCLEAR POWER PLANTS TO ASSESS PLANT AND ENVIRONS CONDITIONS OURING AND FOLLOWING AN ACCIDENT" Dr. Milton S. Plesset's letter to Mr. William J. Dircks dated November 10, 1980, gave the ACRS concurrence in Modified Oraft 3 of Revision 2 to Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an accident," with some exceptions and coments. The following is in response to those comments.
- 1. Dr. Plesset commented that the ACRS concerns regarding potential usefulness of core themocouples in SWRs have been resolved to some extent and noted that the vertical location of these themocouples has not yet been de*cided but suggested that a location close to the top of the core may be desirable.
He also ccamented that further detailed consideration of how the infomation from these instruments will be used will be required before the optimum location can be determined.
Resoonse - The staff agrees with the ACRS that further consideration is necessary before the optimum vertical location can be determined. Therefo re, the guide has been issued with no definitive location specified beyond the provision that there be four thermocouples per quadrant.
- 2. Dr. Plesset commented that the requirements for installed instruments for radiation exposure rates in the environs of a plant are deficient and recommended that the requirements be deleted until suitable guidance can be provided.
Resoonse - The staff agrees with this comment insofar as it pertains to tne Type C variable. Therefore, the variable has been deleted from the Type C list. The discussion with the ACRS concentrated on the use of this variable as a means of detecting releases from the containment from unidentified release points. Since the function of detecting primary containment breach must still be performed, it will be accomplished by monitoring the radiation exposure rates inside buildings such as the auxiliary building, the fuel handling building, the secondary containment, etc., whose inside areas are in direct contact with the primary containment.
It is believed that the highest probability for a breach of the primary i containment will be where penetrations and hatches are located.
-l
. l
To: R. F. Fral ey JAtt 2 3 ;gg)
For completeness, however, the variable " Radiation Exposure Rate in the' Environs" has been retained in the list of Type E variables .(those variables -
to monitor _ release of radioactive materials) since measurement of the variable-provides important infonnation for the radiological emergency response program as well as for the control room operator. Reference is made-in the guide to NUREG-0654, " Criteria for Preparation and Evaluation
- of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" for the detailed requirements of the measurement. ,
Ths' additional guidance suggested by the ACRS as being necessary for .the installed instruments to measure this variable'will be developed and evaluated by NRR as the program' to meet the criteria of NUREG-0664 is impl emented .' Thus, the staff believes that it has been responsive to the '
ACRS connent.
- 3. Dr. Plesset consented that since the design of the instruments of Regulatory Guide 1.97 is closely linked to and may be influenced by their utili:ation in the Emergency Response Facilities, the requirements for these facilities should be decided upon and promulgated promptly or else the implementation schedule of Regulatory Guide 1.97 should be modified accordingly.
Response - The staff agrees with this comment. It is the intent of the staff to issue NUREG-0696, " Functional Criteria for Emergency Response Facilities," within a few weeks. This will allow for the integration of the design of these facilities with the design of the instrumentation provided by Regulatory Guide 1.97, thus, making it unnecessary to modify the implementation date as proposed in the guide.
4 G. A. Arf ot? , Direc @
Division of' Engineering Standards Office of Standards Development 1
i 1
-, - . . . - .- . - - - , . . . - - . . - _ - . ~ . _ . _ . . . . . . _ . -
. , _ _ . - . _ . . _ . _ . . _ _ . , _ _ _ _ . , . - . . , . . . _ . . , - - - . _ , . . , _ . - . , , _ . .- -- .