ML19260C069
| ML19260C069 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 11/23/1979 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Jens W DETROIT EDISON CO. |
| References | |
| REF-GTECI-A-34, REF-GTECI-IP NUDOCS 7912180314 | |
| Download: ML19260C069 (3) | |
Text
.4
.s f *c j
/
w*%
UNITED sT17tW u v v v. 4 La g j m,
j j $ ry j NUCLEAR REGULATORY COMMISSION I1
%'"JI/
c WASHINGTON, D. C. 20555
- .,9+5/ /
%y NOV ' 31979 l
Cocket No. 50-341
(
Dr. Wayne H. Jens Assistant Vice President Engineering & Construction Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226
Dear Dr. Jens:
SUBJECT:
PROPOSED 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" - (FERMI UNIT 2)
The Regulatory staff is revising Regulatory Guide 1.97 to provide more specific guidance than that contained in the guide now being used. A draft of proposed revision 2 of this guide is enclosed (Enclosure 1). The Advisory Corm:ittee on Reactor Safeguards has reviewed proposed Revision 2 of the guide and has agreed to its issuance for comment. is based on the results of Task Action Plan A-34, "Instrumen-tation for t'onitoring Radiation and Process Variables During an Accident" which was initiated in June 1977 to develop more specific guidance concerning implementation of Regulatory Guide 1.97.
A major addition to the current Regulatory Guide 1.97 is the identification of specific parameters to be measured, the range of the measurements and design criteria for the instruments.
Die enclosed draft guide also incorporates the applicable reconmendations in NUREG-0578 "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recomnendations."
The proposed Revision 2 of this guide will have a significant impact on the design of plants such as yours that are currently under review for an operating license. Therefore, we are requesting early comments on proposed Revision 2 from applicants for these plants. We have arranged meetings in Bethesda, Maryland to discuss these comments. We will meet with nine applicants for pressurized water reactors on December 13, 1979 and with five applicants for boiling water reactors on December 14, 1979.
We recuest that you attend the meeting as indicated in the enclosed meeting notice (Enclosure 2) to discuss your comments on the feasibility of designing and installing instruments meeting the requirenents of proposed Revision 2 to Reguletory Guide 1.97 in your plant. An advance copy of major comments and the assccin2d rationale should be given to V. Benaroya, Chief, Auxiliary Systems Branch, CSS, NRC prior to the meeting.
-0**
T 160f 316 X.
7912180 3/4-oc o
n
NOV 2 31979 Dr. Wayne H. Jens
-2 If there are any questions regarding the meeting, call L. L.
Kintner (301) 492-8344.
ine rel,
6
^
/
S.
. Wa rga, Ac Assistant n
Director fo L ght Water Reactors Division of Pr et Management Enclosures :
1.
Draft of Proposed Revision 2 to Regulatory Guide 1.97 2.
Veeting Notice cc w/Encis: See next page 16h317
NOV 2 3 G79 Dr. Wayne H. Jens cc:
Euger.e 3. Thomas, Jr., Esc.
David E. Howell, Esq.
LeBoeuf, Lamo, Leiby & l'acRae 21916 John R 1312 f:ew Hampsi. ire Avenue., N. W.
Hazel Park, Michigan 48030 Washington, D. C.
2C036 Peter A. Marquardt, Esa.
Co-Counsel Mrs. Martha Drake The Detroit Edisnn Company 230 Fairview I
2000 Second Avenue Petoskey, flichigan 49770 Cetroit, Michigan 48226 Mr. William J. Fahrner
[.-
Project Manager - Fermi 2 The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 43226 t'r. Larry E. Schuerman Licensing Encineer - Fermi 2 Detroit Edison Ccmpany 2000 Second Avenue F'
Cetroit, Michigan 48226 Charles Bechhoefer, Esq., Chairman Atomic Safety & Licensing Board
?anel U. S. Nuclear Reculatory Commission Washington, D. C.
20555 Dr. David R. Schink Cesartrent of Oceanography Texas A & M University College Station, Texas 77840 g,
6d fir. Frederick J. Shon p..
Atomic Safety & Licensing Board i,. -.
Panel d-U. S. T'uclear Reculatory Co r.ission l-j.
Washington, D. C.
20555 fir. Jeffrey A. Alson h.'
772 Green Street, Suilding 4
~,i Ypsilanti, Michigan 48197 7
9 PP OG
(\\
~
16M 318
. v..
s LJ
\\
s Drafc 1 October 15, 1979 PROPOSED 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 s
A.
INTRODUCTION Criterion 13, " Instrumentation and Control," of Appendix A, " General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, " Licensing of ecoductian and Utilization Facilities," includes a requirement that instrumentation be provided to monit ir variables and systems for accident conditions as appropriate to ensure adequate safety.
Criterion 19, " Control Room," of Appendix A to 10 CFR Part 50 includes a requirement that a control room be provided from which actions can be taken to maintain the nuclear power unit in a safe condition under accident conditions, including loss-of-coolant accidents and that equipment at appropriate locations outside the control room be provided with a design capability for prompt hot shutdown of the reactor including necessary instrumentation.
Criterion 64, " Monitoring Radioactivity Releases," of Appendix A to 10 CFR Part 50 includes a requirement that means be provided for monitoring the reactor containment at*,osphere, spaces containing components for recirculation of loss-of-coolant accident fluid, effluent discharge paths, and the plant environs for radioactivity that may be released from postulated accidents.
This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations to variables and systems during and foil LICATE DOCUMENT nuclear power plant.
Entire document previously entered into system under:
_[
1.97 N o.
of pages:
October 15, 1979 Value/ Impact Statement of Proposed Revision 2 to Regulatory Guide 1.97, " Instrumentation In Light-Water-Cooled Nuclear Power Plants To Assess Plant and Environs Conditions During and Following an Accident" I.
The Procosed Action A.
Description The applicant (licensee) of a nuclear power plant is required by the Commission's regulations to provide instrumentation to (1) monitor vari-ables and systems for accident conditions as appropriate to ensure adequate safety, and (2) monitor the reactor containment atmosphere, spaces contain-ing components for recirculation of loss-of-coolant accident fluid, effluent discharge paths, and the plant environs for radioactivity that may be released from postulated accidents.
This revision to Regulatory Guide 1.97 proposes to improve the guidance for plant and environs monitoring during and follow-ing an accident.
B.
Need Regulatory Guide 1.97 was issued as an effective guide in August 1977.
At the time the guide was issued it was recognized that more specific guid-ance than that contained in the guide would be required. However, the diffi-culty in developing the guide to the point where it could be initially issued was evidence that experience in using the guide as it then existed was essential before further development of the guide would be meaningful.
At the time Regulatory Gui" ' "
tive guide (August 1977), the s ments for Monitoring Radiation DUPLICATE DOCUMENT Entire document previously g(
entered into system under:
W y 2 0.$,g g g p 16Df 320 xNO No. of pa es: