ML19289F638
| ML19289F638 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/11/1979 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| LAC-6338, NUDOCS 7906150217 | |
| Download: ML19289F638 (5) | |
Text
e DAIRYLAND POWER COOPERATIVE Ea Groue, OLasta 54601 June 11, 1979 In reply, please refer to LAC-6338 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation ATTN:
Mr. Dennis L.
Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors U.
S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 SYSTEMATIC LVALUATION PROGRAM (SEP) TOPICS III-ll AND III-5. A - ADDITIONAL INFOR*4ATION -
HIGH PRESSURE CORE SPRAY DISCHARGE LINE
Reference:
(1)
NRC Letter, Ziemann to Linder, dated April 18, 1979.
(2)
DPC Letter, LAC-6316, Linder to Director of Nuclear Reactor Regulation, dated September 26, 1978.
Genrlemen:
Your request for additional information (Reference 1) on SEP Topics III-11 and III-5.A has been reviewed and a single copy of the compilation of this additional information is attached to this response as Enclosure 1.
forwarded Your request followed a review of NES Report 81A0091, by Reference 2, which is referenced in this response but not resubmitted.
If there are any questions concerning this response, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE h/2A4 Frank Linder, General Manager FL:RES:af Enclosure 2229
- 2h6 cc:
J. Keppler, Reg. Dir., NRC-DRO III w / Enclosure 1 only 7906150,Ri7
ENCLOSURE 1 Additional Information for Audit of HPCS Discharge Line Analysis
(
NRC REQUEST:
1.
Design specification uhich vill confirm certain data auch as design and operating temperaturea, pressures and material sp ecifica tione.
DPC RESPONSE:
Pages 3-6, 3-7, 3-27 and 3-28 of Allis-Chalmers' LACBWR piping system specification #41-585 revised April 3, 1964 (Attachment A to this enclosure), and Table A-1, Appendix A, of NES Report 81A0091 (submitted by Reference 2), list the design temperatures, pressures and material specifications.
??C REQUE3::
Cc.mr u ta r licting uced ac input to your ccepu cr code.
DPC RESPONSE:
The computer listing is Attachment B to this enclosure.
- P:== LUES:-
3.
ie: ailed piping dracings and/or isometrica indicating all rcrtinent iimensicnc, bend radii, veld and valuc locatione.
DPC RESPONSE:
The following drawings are Attachment C to this enclosure:
Pittsburg Piping & Equipment Co.,
Isometric Drawing / Sketch No.:
35202 - Revision 3 - Revision to Core Spray Pump Suction Piping.
10872 Revision 4 - Fuel Storage Well Flooding Piping and Sodiun Pentaborate Suction Piping 10872 Revision 3 - Sodium Pentaborate Discharge Piping 10872-274 - Revision 3 - 1 " Emergency Core Spray Pump Suction and Discharge 10872-275 - Revision 1-1" Puel Well to and Fron Portable Demineralizer 2229 327
_1_
' ENCLOSURE 1 - Additional Information for Audit of HPCS Discharge Line Analysis (Cont'd)
DPC Letter, Towsley to Hussein-NES (LAC-3477) dated October 29, 1975.
Sargent & Lundy Engineering Drawings, Nos:
41-503-363 - Revision P - Reactor Plant Piping Plans "C-C" "D-D" 41-503-368 - Revision K - Reactor Plant Piping Section "J-J" LACBWR Safeguards Report for Operating Authorization, ACNP 65544:
Figure A.17 Figure A.18 Figure A.20 Page 4 Appendix A, Spec. $41-473, Rev. 3 Page 4 Appendix A, Spec. #41-473, Rev. 3 Page A.4 - Appendix A URC REQUEST:
4.
Lict cf ripe support detaila, including typce, locationc, e <*~fnecace and pre!cado (i. e., hot and cold loada).
DPC RESPONSE:
The locations of existing and recommended additional pipe restraints are shcwn in Figure 3-1 of NES Report 81A0091.
The location of existing piping suspension (hangers, etc. ) and dimensional character-istics used in NES Report BlA0091 were determined from the piping drawings and visual inspection and measurements at the LACBWR site.
The stif fness of pipe supports were estimated fron the field infor-nation.
Dimensional data and stiffness data used in NES Report 81A0091 are unavailable.
Dimensional data and description of pipe supports based on recent visual inspection is included in Attachment D to this enclosure.
There are no preloads (i.e.,-hot and cold loads) specified for the pipe supports.
The HPCS discharge line is essentially a small diameter
( 2-1/2" diame ter and less) cold passive piping systen except at the time of HPCS initiation.
There is adequate flexibility in the piping systen to accommodate thermal expansion associated with HPCS initiation.
- .RC RE,?UEST:
E.
Lia: cf valrc iccaticnc, v:ights and cccentricifica.
DPC RESPONSE:
Valve locations, weights and eccentricities are given in Table A-ll, Appendix A of NES Report 81A0091 (submitted by Reference 2).
2229 328
, ENCLOSURE 1 - Additional Information for Audit of HPCS Discharge 7
Line Analysis - (Cont'd)
NRC RECUEST:
G.
List of any anchor movemente (thermal and ceienic) and Z c ca ti c >:c.
DPC RESPONSE:
Thermal and seismic anchor moverents and locations are given in Table A-III, Appendix A of NES Report 81A0091 (submitted by Reference 2).
URC REQUEST:
7.
Detai:cd thermal gradien: informaticn.
DPC RESPONSE:
Information regarding thermal gradient are provided in Appendix E of NES Report 81A0091 (submitted by Reference 2).
URC REQUES :
8.
Descripticn cf cry special fittinge er ecmconanic v r c e c r. : cn the piping system.
DPC RESPONSE:
As part of the plant modification associated with sensitized nozzle replacement, the original butt welded connection between the stainless steel (Type 304) pipe and the ASTM B166 incone?
bar of the reactor vessel nozzle was replaced by socket weld #ittings.
Reference:
Southwest Research Special Report SwRI Project 17-2757, Contract No. AT ( ll-1) - 12 2 8, "The Replacement of Selected Components in the LACBWR Primary Coolant Piping System," 14 August 1970.
URC REQUEST:
9.
If applicable, any imposed forces ar.d momento due to relief valve discharge, connected linea and componente.
DPC RESPONSE:
There are no forces and moments imposed on the HPCS discharge line from the relief valve discharge, connected lines and components.
2229 329 ENCLOSURE I - Additional Information for Audit of IIPCS Discharge Line Analysis - (Cont'd)
NRC EEGUEST-10.
Please confirm that the follouing accumptions are valid:
a.
- 2 compc>
- cr::e :ve b :< : : s:!c' (f * :a :: ] m:i ;' r;; '
(no longitudinal velds).
b.
All componente meet ANSI B16. 9 and ANSI B16. 28 etandardo.
c.
The recuiremer:te cf ASME Jode, ac e tic r: III, ::d -
article NB-3640 or NC-3C40 are satisfied.
DPC RESPONSE:
There are no longitudinal welds in the HPCS discharge line.
a.
There are, however, socket welds in the small diameter (2" diameter and less) HPCS discharge piping.
b.
Allis-Chalmers LACBWR piping specification 41-585 specified ANSI B16.9 for the fittings of 2 " and above diameter pipes and ANSI B16.11 for the fittings cf 2" and craller diareter pipes.
c.
The HPCS discharge line piping system meets the pressure designs requirements of ASME Code,Section III, subarticle NB-3640 or NC-3640.
2229 330