ML17174A410
| ML17174A410 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/17/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Peoples D COMMONWEALTH EDISON CO. |
| References | |
| TASK-03-05.B, TASK-3-5.B, TASK-RR NUDOCS 8002070004 | |
| Download: ML17174A410 (3) | |
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Local PDR ORB REading Docket NQ. *50-237 NRR Reading DEisenhut RVollmer OELD
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DLZiemann PO'Connor
. HSmith..
Mr. o~ Lou1~ People~
Director *of Nuclear*U.censing Conm1onwealth ~d1son Company N?IC/TERA/ ACRS (16).
~Crutchfield. (2)
P. o. Box 76.7 Chicago, 1.111 nois
- 60690
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_Pear Mr.* Peopl.es;
--' *.. *.. RE:, REQUEST FOR ADDi'TiONAL INFORMATION*
TOPIC -u 1-s.0* P1pe* Break :outs1 de Containment*
.DRESDEN UNIT~*.
JAN.1 7 1980 To corit1nue our review o_f Syste~atJc Evaluation Program TQpic. UI-5.B P1pe
,._,. *Break Outs1de-.Conta1nment; we r:equest that you s*ubmi t the *1nfonnation des-cd bed in t~e enclosure..
- You~ respo~se is requested ~1th1~ 3o :days of.rece1pt-~_of. thi*s le~ter so* tba*t we ~an'._rna.intain our review *s*chedule~.*
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Enclosure:
Request for Add-1 ti ona 1
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- .Dennis L. Zi:emann, Ch.1ef
, ".,.: Operating Reactors Branch f/2. *.
......_ 'D1v1.s1on of Operating Reactors, *.. * -~~,. *.
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NRC_FORM 318 (9-7.6) NR_CM Q240
. *u.s. GOVERNMENT PRINTING OFFICE: 1979:289-3'69
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-~r. D. Louis Peoples cc
- Isham, Lincoln & Beale Counselors at Law Cne First National Plaza, 42nd Floor Ch{cago, Illinois 60603
~r. B. B. Stephenson Plant Superintendent Dresden Nuclear Power Station Rural Route #1 P.orris, Il 1 inoi s 60450
- Anthony Z. Reisman
~atural Resources Defense Council 917 15th *Street, N. W.
~ashington, D. c.
20005 U. S. Nuclear Regulatory Commission ATTN:
Jimmy L. Barker P. O. Box 706 Horris, Illinois 60450 Susan N. Sekuler Assistant Attorney General Env1ronmental Control Division 188 W. Randolph Street Suite 2315 Chicago, Illinois 60601
~orris Public Library 604 Liberty Street
~orris, Illinois 60451 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Horris, Illinois 60450 e.*
January. 17, l 980
- Depart~ent of Public Health ATTN:
Chief, Division of Nuclear Safety 535 West.Jefferson Springfield, Illinois 62761 Directo;, Technical Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crysta1 Mall #2 Arling:on, Virginia 20460 U. S. Environmental Protection Agency Federa1 Activities Branch Region V Office ATTN:
EIS COOR DI NA TOR 230 So~th Dearborn Street Chicago, Illinois 60604 Neil Smith Commonwealth Edi son Cm.. pany P. 0. Box 767 Chicago, Illinois 60690
REQUEST FOR ADDITIONAL INFORMATION SEP TOPIC III-5.B, PIPE BREAK.OUTSIDE CONTAINMENT DRESDEN UN IT 2
- l. Provide a.comparison of the design of the containment penetration piping outside containment between the containment and the first containment isolation valves for the main steam lines, isolation condenser steam and condensate lines, and reactor water cleanup inlet line with the provisions of section B.1.b of Branch Technical Position MEB 3-1 (appended to Standard Review Plan 3.6.2) in sufficient detail to identify the.degree of confonnance with and deviations from these provisions.
- 2. Provide a comparison of the design of the containment penetration piping outside containment for the isolation condenser steam line and reactor water cleanup inlet line with the provisions of section S.2.C of Branch Technical Position ASB 3-1 (appended to Stand~rd Review Plan 3.6.1) in sufficient detail to identify the degree of conformance with and deviations from these provisions.
- 3. Provide an evaluation of the cbnsequences of a postulated main feed system high energy line break on the mezzanine floor of the turbine building.. Consider the postulated loss of offsite power and a concurrent single active failure in accordance with the provisions of section B.3 of Branch Technical Position ASB 3-1 *.
- 4. Provide additional details of the corrective actions implemented to prevent flooding of the Unit 2 diesel generator control cabinet as described in Reportable Occurrence Report 79-52 of October 17, 1979. Discuss the capability of the corrective measures (RTV sealant) to prevent disabling the diesel generator following a postulated main feed system pipe break on the mezzanine floor.
- 5.
Provide an evaluation of the consequences of flooding both 4 kV switchgear 23-1 and 24-1 to the depth of the curb surrounding the switchgear panels from a postulated reactor building closed cooling water system leak (spray) on the 545' elevation of the reactor building.