ML19262C092
| ML19262C092 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/24/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| LAC-6752, NUDOCS 8001280284 | |
| Download: ML19262C092 (8) | |
Text
'
IMIItYLAND I'0 WEIT COUI*EIRATIVE Sa Crone, Ohcoudn
$4601 January 24, 1980 In reply, please refer to LAC-6752 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 APPLICATION FOR AMENDMENT TO LICENSE
Reference:
(1)
NRC Letter, Reid to Madgett, dated April 22, 1976.
(2)
DPC Letter, LAC-4271, Madgett to Reid, dated October 13, 1976.
(3)
NRC Letter, Reid to Madgett, dated January 10, 1978.
(4)
DPC Letter, LAC-6280, Linder to Ziemann, dated May 11, 1979.
(5)
DPC Letter, LAC-6429, Linder to Ziemann, dated July 27, 1979.
Gentlemen:
An application to amend Provisional Operating License No. DPR-45 was requested in Peference 4.
The requested smendment involved proposed changes to Technical Specifications for the La Crosse Boiling Water Reactor (LACBWR) which deal with the Inservice Inspection Program.
The LACBWR Project Officer presented LACBWR a request for additional information based on review of Reference 5, the plans and requests for relief of certain inservice testing requirements.
The following information is presented:
Class I Componente 1.
The p?opoecd weld inapaction program requesta 'ratief from code required examinatione due to high radiation consideratione_ for the following systema or portione of systema:1816 0981, i
1-8001080
Mr. Dennis L.
Ziemann, Chief LAC-6752 Operating Reactors Branch #2 January 24, 1980 Reactor Vecect Forced Circulation Main Stcam Systen Feedvater Sycten Baron Injecticn System While the etaff renogni:.ea that necting code requiremente nay be impractical for 'hc cyctems listed abovc, provide ductifi-cation for not inopcoting sciccted pcrtione of the affccted ccnponen:o and velde in the high radiation areas using an alternate inspection prcaran cr other UDE nothodc.
DPC RESPONSE:
Reactor Vessel We would be able to double the examinations performed on vessel to flange weld, the longitudinal weld of the uppermost cylindrical shell section and upper shell course to intermediate shell course welds (nelds 3, 4 and 5, respectively, Fig. A-1) as an alternate.
Welds in the core region are located 4 inches from the external thermal and biological shield wall, in which 2 inches of insulation exists.
Therefore it is considered inaccessible.
All 39 penetrations and the one capped nozzle in lower reactor vessel head are enclosed in the vessel support ring, which is located a mean clearance of approximately 16 inches from the periphery of the penetrations.
Main Steam Systen These welds are located on a 10-inch pipe in a 2-foot square pipe chase and are considered inaccessible.
The revised table for Relief for Class I Components Requiring ISI to ASME XI is submitted as a replacement for the table of the same title which was part of Enclosure 1 of Reference 5.
You will note that the requests for relief have been substantially reduced.
The only thing left on the relief request table for Forced Circulation and Feedwater are some integrally welded hangers.
We believe that the volumetric examinations should be waived based on high radiation and the necessity for insulation removal and replace-ment.
This insulation was not installed to be removable.
1816 099 2-
Mr. Dennis L.
Ziemann, Chief LAC-6752 Operating Reactors Branch #2 January 24, 1980 2.
Xour an'bmittat states that precouve retaining botting for the Forced Circulation pumpe vitt be examined volumetrically and surface when the pump is dicaecembled for other reasons.
Is the Forced Circulation pump disaaeembled on a routine basis for maintenance?
A teo, recognizing high radiation consider-atione, can a portion of the totat required botte be examined volumetrically?
DPC RESPONSE:
No.
The Forced Circulation Pump is not disassembled on a routine basis for maintenance.
At the present time, the configuration of the bolts prevents a meaningful volumetric examination.
The bolt is 13-9/16 inches long with a diameter of 2 inches and there is a 9/16 inch hole through the length of it.
Xour submittat states that pump casinge velds and pump casings vill be examined every 20 years, hcuever, code requires examin-ation every lo yeare, please explain this dicarepancy.
DPC RESPONSE:
This was a typographical error - see enclosed replacement sheet.
Class II Componente 1.
Please identify those systems or portione of systems that vere excluded from examination due to IWC-1220(b) and (c).
DPC RESPONSE:
That portion of the shutdown condenser condensate return line, between the shutdown condenser and air operated isolation valves, which does not function during normal reactor operation, has been exempted from the examination requirements of IWC-2520 in accordance with IWC-1220(b).
LACBWR has taken no exemptions from the examination requirements of IWC-2520 in accordance with IWC-1220(c).
1816 100 Mr. Dennis L.
Ziemann, Chief LAC-6752 Operating Reactors Branch a2 January 24, 1980 If there are any questions concerning this submittal, please contact us, Very truly yours, DAIRYLAND POWER COOPERATIVE
)'
m A<
Frank Linder, General Manaaer FL: HAT:af cc:
J.
Feppler, Peg. Dir., !!RC-DRO III STATE OF UISCONSI:i )
)
COUNTY OF LA CROSSE)
Personally came before me this day of January,. 1980, the above named Frank Linder, to me known to be the person who executed the foregoing instrument and acknowledged the same.
Arw
,76td Notary Pubidc, La Crosse County, Wisconsin My Commission expires March 2, 1980.
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EXAMINATION I t.S PE CT I n" CATEGORY REGUIRfD ITEM TABLE NO.
IWB-2500 IDENTIFICATI0i1 0F WElh OR Cn!&ONfNT BY IWB-Pf'00 BASIS FOR REQUESTING REL:!
10" MAIN STEAM PIPING 84.5 B-J PIPE TO PIPE, WELD #19 VOLUMETRIC NO PERSONNEL ACCESS IN THIS AREA DUE TO THE SMALL INTERIOR OF THE PIPE CHASE PIPE TO PIPE, WELD #20 CAVITY.
l PIPE TO PIPE, WELD #21 Y
PIPE TO PIPE, WELD #22 MISCELLANEOUS PIPING COMPONENTS:
MAIN STEAM SYSTEM PIPING HANGERS B4.9 B-K-1 INTEGRALLY WELDED ATTACHMENTS #MS-102 VOLUMETRIC RADIATION LEVELS OF 1100 TO 1500.R/HR GENERAL AREA AND 2-3 R/HR SURFACE WOULD CAUSE EXCESSIVE EXPOSURE PER WELD EXAMINATION.
FEEDWATER SYSTEM PIPING HANGERS B4.9 B-K- 1 INTEGRALLY WELDED ATTACfiMENTS #RF-113 VOLUMETRIC B4.9 B-K-1 INTEGRALLY WELDED ATTACHMENT #RF-II4 VOLUMETRIC FORCED CIRCULATION SUCTION HEADER 1
PIPING HANGERS
{
B4.9 B-K- 1 INTEGRALLY WELDED ATTACHMENTS FC-101 VOLUMETRIC B4.10 B-K-1 h INTEGRALLY WELDED ATTACHMENT FC-102 VOLUMETRIC
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