ML19260C074
| ML19260C074 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 11/23/1979 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Borgmann E CINCINNATI GAS & ELECTRIC CO. |
| References | |
| REF-GTECI-A-34, REF-GTECI-IP, RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 7912180323 | |
| Download: ML19260C074 (3) | |
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f asce, UNITED STATES i0..,/i NUCLEAR REGULATORY COMMISSION h,$4/l 4
b WASHINGTON, D. C. 20555 i*
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.:. 4 y NOV 2 31979 Occket No. 50-358 Nr. Earl A. Ecrg ann Vice President - Engineering The Cincinnati Gas and Electric Canpany P. O. Sox 950 Cincinnati, Chio 45201
Dear Mr. Borgmann:
SUBJECT:
PROPOSED REVISION 2 TO REG'JLATORY GUIDE 1.97 " INSTRUMENTATION FOR LIGHT-WATER-COOLED NUCLEAR PCWER PLANTS TO ASSESS PLANT AND ENVIRONS CONDITICNS CURING AND FCLLOWING AN ACCIDENT" (ZIMMER UNIT 1)
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 enclosec (Enclosure 1). The Advisory Comittee on Reactor Safeguards has revieved proposed Revision 2 of the guide and has agreed to its issuance for ccmment. is based on the results of Task Action Plan A-34, "Instrumen-tation for Monitoring Radiation and Process Variables During an Accident"
'shich 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 cf the measurements and design criteria for the instruments.
The enclosed draft guide also incorporates the applicable recommendations in NUREG-0578 "311-2 Lessons Learned Task Force Status Recort and Short-Term Recenmendations."
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 acclicants for these plants. We have arranged meetings in Bethesda, Maryland to discuss these coments. We will meet with nine applicants for pressurized water reactors on December 13, 1979 and with five applicants for boiling water reactors on Cecember 14, 1979.
e request 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 requirements of proposed Revision 2 to Regul ato y Guide 1.97 in your piant. An advance copy of major comments and the mcci:ted rationale should be given to V. Benaraya, Chief, Auxiliary Systems Brarcc., 'i 1RC orior to the meeting.
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Mr. Earl A. Borgmann U C! 2 s' :37' If there are any questions regarding the meeting, call L. L.
Kintner (301) 492-8344
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. / rga, Aq ng Assistant Director for ' ht Water Reactors Division of Project Management Enclosures :
1.
Oraft of Proposed Revision 2 to Regulatory Guide 1.97 2.
S'eeting f:otice cc w/Encis:
See next page
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16M 343
NOV 2 31979 cc:
-roy 3. Conner, Jr., Esq.
David 3. Fankhauser, Pri C.on er, core. Corber 3569 Nine "iie Road
,ennsylvania n. venue,,..
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cincinnati, un1o
-:c; Washington,.0.
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Or. Frank F. Hooner "r. William J. Moran School of Natural Rescurces aenera,i counset
,,n1versity c..ichican e
~he Cincinnati Gas anc E'ectric Ann Arcor, "ichigan' 47109 I
- crcany
- - O. Box 960
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Stephen Scnumacner Cincinnati, Ohio 45201 Miami Valley Power Pro.iect P. O. Box 252 "r.
.<illian G. Porter, Jr.
Dayton, Ohio 45401 Porter, Stanley, Arthur anc :latt Ps. Augusta Drince, Cns;rperson 37 <.'est 3 road Street 501 Stanley -venue r 'iumous, m's.ic
-;2ia cincinnati, Ohio
-:'ce c
v fir. Steven G. Smith, Manacer Charles Sechncefer, Esc., Chai rman 5ngineering & : aject Controi Atomic Safety & Licensing Boarc The Dayton Pcwer and L:gnt Panei Comcany U. S. Nuclear Regulatorv Commission 3
O. 5cx 1247
';asnington, 3. C.
20555 Cayton, Ohio 45 01 Mr. Glenn 3 3 ri nh J. Ocbert Newlin, Counsel Atomic Safety and The :ayton Pcwer arc Lignt Scarc Panel Ccmcany U. S. ' uclear Deculatc'-
Commission
- . C. Box 1207 Washington, 2. C.
205:5
- ayton, Chic 05 01 Le a n S.
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"r. James J. Fijnn 3454 Ccenell Slace Manager, Licensing Cincinnati, Ohio 45220 Er.vi ronmental Affairs The Cincinnati Gas anc Peter Heile, Esq.
Electric Ccmcany Assistant City Sciicito-P
- 0. 3ax 350 Rocm 214, Ci".y Hall Cincinnati, Ohio J5201 Cincinnati, ^hio a522?
"r. J. 3 Fenstermaker Atomic Sa'ety anc Lice'1 sinc 3carc Senior Vice President-Operations Panel Columbus and Southern Ohio U. S. Nuclear Regulat>, Commission Electric Company Wasnington, D. C.
20553 215 Nortn Front Street Cciumbus, Ohio 02215 Atcmic Safety and Lice" sinc Acceal Scart
- 3. ':uc' ea r 2ecul a ta-Comrissicn Wasnington, J. C.
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.5, a. % l Drafc 1 Occober 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 i
A.
INTRODUCTION Criterion 13, " Instrumentation and Control," of Appendix A, " General Design
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Criteria for Nuclear Power Plants," to 10 CFR Part 50, " Licensing cr Production and Utilization Facilities," includes a requirement that instrumentation be provided to monitor 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 atmosphere, spaces containing comconents 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 ccmplying with the Commission's regulations to variables and systems during and fol DUPLICATE DOCUMENT nuclear power plant.
Entire document previously entered into system under:
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Oc:ober 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 Procesed 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 frem 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.
3.
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 p Int where it could be initially issued was evidence that experience in using the guide as it then existec was essential before further development of the cuide would be meaningful.
At the time Regulatory Gui
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tive guide (August 1977), the s ments for Monitoring Radiation DUPLICATE DOCUMENT Entire document previously entered into system under:
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No. of pages:
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1691 346