ML19256F986
| ML19256F986 | |
| Person / Time | |
|---|---|
| Site: | Fermi, Susquehanna, Farley, LaSalle, Zimmer, Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 11/23/1979 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Barton A ALABAMA POWER CO. |
| Shared Package | |
| ML19256F987 | List: |
| References | |
| RTR-REGGD-01.097 NUDOCS 7912270167 | |
| Download: ML19256F986 (3) | |
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UNITED STATES
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%...f;l NOV e 31979 Cocket No. 50-364 s
Mr. Alan R. Barton Senior Vice President Alabama Power Company 500 North 18th Street Si rni nghan, Al abama 35291 Cear vr. 3arten:
SU5JECS PROPOSED REVISION 2 TO REGULATCRY GUIDE 1.97 " INSTRUMENTATION FCR LIGHT-WATER-CCOLED NUCLEAR PCWER PLANTS TO ASSESS PLANT AND ENVIRONS CONDITIONS DURING AND FOLLCWING AN ACCIDENT" (FARLEY UNIT 2)
The :egulatcry staf' is revising Regulatory Guide 1.97 to provide more specific guid.nce than that contained in the guide now being used. A draft of proposed revi ion 2 cf this guide is enclosed (Enclosure 1). The Advisory Ccmittee on Reactor Safeguards has reviewed proposed Revision 2 of the guide and has agreed to it. issuance for ccmment. is based on the results of Task Action Plan A-34, "Instrumen-tation for Mcnitoring Radiation and Process Variables During an Accident" which was initiated in June 1977 to develop more specific guidance concerning imple.:entation of Regulatory Guide 1.97.
A major addition to.the current Regulatory Guide 1.97 is the identification of specific pararceters to be measured, the range of the measurements and design criteria for the instruments.
The enclosed draft guide also incorporates the applicable recommendations in NU'iEG-0578 "3I-2 Lessens Learned Task Force Status Report and Short-Term Reccm ecdations."
The crocesed Revision ? 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 recuesting early ccaments on proposed Revision 2 from apolicants for these plants. We have arranged meetings in Bethesda, Maryland to ciscuss these comments. We will meet with nine applicants for pressurized water reactors on December 13, 1979 and with five applicants for boiling water reactors en December 14, 1979.
We reatest that you attend the meeting as indicated in the enclosed meeting notice ', Enclosure 2) to discuss your cccments on the feasibility of designing and installing instruments meeting the requirements of procosed Revision 2 to Regulatory Guide 1.97 in your plant. An advance copy of major comments and the asscciaMd rationale should be given to V. Benaraya, Chief, Auxiliary Systems 2rancn, JSS, NRC crior to the meeting.
1821 074 7912270
r. Alan R. 3arton NCV 2 31979 If there are any questions regarding the meeting, call L. L.
Kintr.er (301) 492-83'*.
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Enclosures:
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Craft of Proposed Revision 2 to Regulatory Guide 1.97 2.
eeting Notice cc w/ Encis : See next page 182% 075
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Draf 1 Occober 15, 1979 PROPOSCD REVISION 2 TO REGULATORY GUIDE 1.97 INSTRUMENTATION FOR LIGHT-WATER-CCOLED NUCLEAR POWER PLANTS TO ASSESS PLANT AND ENVIRONS CONDITIONS DURING AND FOLLCWING AN ACCIDENT A.
INTRODUCTION Criterion 13, " Instrumentation and Control," of Appendix A, " General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, " Licensing of Production and Utili;:ation Facilities," includes a requirement that instrumentation be provided to monitor variables and systems for accident conditions as acpropriate to ensure adequate safety.
Criterion 19, " Control Room," of Aopendix 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 aopropriate locations outside the controi room be provided with a design capability for prc=pt hot shutdown of the reactor including necessary instrumentation.
Criterion 64, " Monitoring Radioactivity Releases," of Appendix A to 10 CFR Part 50 includes a recuirement that means be provided for monitoring the reactor containment atmosphere, spaces containing comoonents 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 describas a :ethod acceptable to the NRC staff for complying with the Commission's regulations to -~ 9
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variables and systems during anc foi nuclear power plant.
Entire document previously entered into system under:
wo79/c2G/066(o9 182% 077 1-No. of pages:
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