ML19290C085
| ML19290C085 | |
| Person / Time | |
|---|---|
| Issue date: | 06/11/1979 |
| From: | Szukiewicz A Office of Nuclear Reactor Regulation |
| To: | Deyoung R, Mattson R, Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19290C086 | List: |
| References | |
| REF-GTECI-A-24, REF-GTECI-EL, TASK-A-24, TASK-OR NUDOCS 8001090143 | |
| Download: ML19290C085 (3) | |
Text
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'o UNITED STATES
[ j,,.. q (,j NUCLEAR REGULATORY COMMISSION E
WASHINGTON,0. C. 20555
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Jt;N ! ' 1979 MEMORANDU!! FOR: fluitiple Addresses FR0ft:
A. J. Szukiewicz, Instrumentation and Control Systems Branch Task Manager A-24 THRU:
R. M. Satterfield, Chief, Instrumentation and Control Systems Branch, DSS
SUBJECT:
DRAFT #3 INTERIM POSITION - ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT (TASK A-24)
The enclosed draft of the staff's Interim Position on environmental qualification is provided for your concurrence.
This report incorporates the comments that have been submitted following the issuance of Draft #2 on November 30, 1978.
To facilitate the review, the additions to the position have been identified by enclosing them in brackets
([]). The information that has been deleted is shown with a dashed line (--)
through it. The major change, other than those indicated in the enclosure, is the deletion of positions for operating plants (i.e. Category III requirements in Draft #2). The positions for operating plants will be developed later by D0R pending their evaluation of several SEP plants currently under review. This change in scope has been agreed to by both DSS and DOR.
Resolution has been achieved on all of th significant coments submitted (as indicated in the enclosure) with one exception. D0R suggests that the methodology to be used for determining radiation values (defined in this draft starting on page 7) is overly complex, and that a more simplified approach should be developed.
I have discussed the possibility of revising the methodology with DSE (L. Soffer) and concluded that, because of manpower limitations, this could not be accomplished in a timely manner.
In my view, delaying the issuance of this report to simplify the present approach is not warranted.
In order for this report to be beneficial to the public, industry and the staff it is important that it be issued as soon as possible. Therefore, I request that only those coments which are significant and must be included in order to achieve concurrence be submitted. Comments and/or concurrence are to be submitted by COB June 22, 1979.
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x A. Sz ictew cz, Task ya ger A-24 Instr ation an(C trol Systems
..Bfanch, DSS 1730 224 io 8001090 l m."
Multiple Addressees R. J. Mattson, Director, DSS, NRR V. Stello, Director, DOR, NRR R. DeYoung, Director, DSE, NRR S. Hanauer, Director, Unresolved Safety Issues Program R. Vollmer, Assistant Director for Systems & Projects, D0R B. Kreger, Assistant Director for Site Analysis, DSE R. Tedesco, Assistant Director fer Reactor Safety, DSS B. Grimes, Assistant Director for Engineering Projects, D0R G. Lainas, Chief, Plant Systems Branch, DOR D. Tondi, Section Leader, Plant Systems Branch, D0R F. Rosa, Chief, Power Systems Branch, DSS A. Bennett, Power Systems Branch. DSS T. Novak, Chief, Reactor Systems Branch, DSS S. Israel, Section Leader, Reactor Systems Branch, DSS W. Butler, Chief, Containmer.t Systems Branch, DSS J. Zwolinski, Containment Systems Branch, DSS G. Bennett, Chief, Research Support Branch, DSS R. Feit, Research Support Brznch, RSR
- 9. Houston, Chief, Accident Analysis Branch, DSE L. Soffer, Accident Analysis Branch, DSE R. Satterfield, Chief, Instrumentation and Control Systems Branch, DSS T. Dunning, Section Leader, Instrumentation and Control Systems Branch, DSS M. Srinivasan, Section Leader, Instrumentation and Control Systems Branch, DSS R. Scholl, Instrumentation and Control Systems Branch, DSS V. Moore, Acting Assistant Director for Plant Systems, DSS V. Benaroya, Chief, Auxiliary Systems Branch, DSS F. Akstulewicz, Accident Analysis Branch, DSE Z. Rosztoczy, Chief, Analysis Branch, DSS D. Davis, Ch af, Systematic Evtluation Branch, D0R D. Mcdonald, Systematic Evaluation BrancF, D0R S. Pawlicki, Materials Engineering Branch, DSS J. Halapatz, Materials Engineering Branch, DSS C. Long, Technical Assistant for Plant Systems, DSS D. Sullivan, Reactor Systems Standards Branch, DES 1730 225 O
i Table of Contents Page Introduction i
Discussion jjj I.
Qualification Parameters Inside Containment IA. Temperature and Pressure for LOCA Conditions......
1 3
IB. Submergence and Chemical Spray.............
A IC. Temperature and Pressure for MSL3 Conditions......
ID.
Radiation Inside and Outside Containment.
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II. Temperature, Relative Humidity and Other Environments for Outside Containment 15 16 III. Qualification Methods....................
IIIA. Qualification by Test 19 21 IIIB. Margins 22 IIIC. Sequence...
24 IIID. Aging 26 IIIE. Other Qualification Methods IV.
Quali fication Doctmentation.................
27 Appendix A (Attachment 1)
Page 1 of 1 Appendix A (Attachment 2)
Page 1-5 of 5 Appendix B Page 1 of 1 Appendix C through G Page 1-54 of Sa Appendix H Page 1-4 of 4 1730 226