ML19350B341
| ML19350B341 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/30/1981 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-80-13, LAC-7354, NUDOCS 8103200296 | |
| Download: ML19350B341 (4) | |
Text
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- 1 A CROSEF MsCONSW WO1 (608; 786 4000 January 30, 1981 In reply, please refer to LAC-7354 DOCKET NO. 50-409 Mr. James G. Keppler Regional Director U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 IE BULLETIN NO. 80-13 (SUPPLEMFNT)
References:
(1)
NRC Letter, Keppler to Linder, dated May 12, 1980.
(2)
DPC Letter, Lin,er to Keppler, LAC-7316, dated Jaritary 13, 1981.
Dear Mr. Keppler:
Enclosed, herewith, is supplementary information related to the 1980 augmented inservice inspection of high pressure core spray piping at LACBWR (Reference 2).
The inspection was performed in ra6ponse to NRC's IE Bulletin No. 80-13
" Cracking in Core Spray Spargers" (Reference 1).
This letter provides additional detail of the areas of inspection in LACBWR's high pressure core spray bundle and connecting piping.
The examination areas are listed in the attached table and identified in the enclosed sketch.
As previously stated, the configuration of LACBWR's high pressure core spray system does not incorporate spargers.
No evidence'of intergranular stress corrosion cracking in welds or piping was found for the areas examined.
If.you have any questions regarding this supplemental submittal, please contact us.
f Very truly yours, 37 g;
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DAIRYLAND PCi ER COOPERATIVE W'
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. Frank Linder, Gcneral Manager
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Enclosures '810 32 0 0 Af6 Q
,FEB 13 1981
0 Mr.. James G.
Keppler, Regional Director January 30, 1981 U. S. Nuclear Regulatory Commission LAC-7354 cc:
Director, Division of Reactor Operations Inspection Office of Inspection and Enforcement U. S. Nuclear Regulatory Comission Washington, D.
C.
20555 NRC Resident Inspectors
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y, LA CROSSE BOILING WATER REACTOR 1980 AUGMENTED HPCS SYSTEM INSERVICE INSPFCTION
SUMMARY
(IE BULLETIN 80-13)
Examination Area Mf(hd Identification Indications Remarks No.
Type Configuration 1
B-W Pipe-to T PT None 100% of Weld Length 2
B-W Pipe-to-T PT None 100% of Weld Length 3.
B-W Pipe-to-T PT None 100% of Weld Length 4
'S-W Pipe-to-Flange PT None 100% of Weld Length 5
S-W
. Pipe-to-Flange PT None 100% of Weld Length TC 20% of Weld Length Pipe Surface TC None 10% of Area 5-7 7
B-W Pipe-to-Ell TC None 30% of Weld Length 4
8 B-W Pipe-to-Ell TC None 30% of Weld Length 16-S-W Fittings VT None 100% (350 PSIG Leak Test) 87 NOTATION:
B-W (Butt-Weld); S-W (Socket Weld); PT (Penetrant Test)
VT (Visual Test); TC (Television Camera) with resolution of <.002 inch l
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