ML20049J161

Requests Addl Info Re Inservice Insp Relief Requests.Info Requested within 30 Days of Ltr Date

ML20049J161
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/08/1982
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Linder F DAIRYLAND POWER COOPERATIVE
References
LSO5-82-03-041, LSO5-82-3-41, NUDOCS 8203120196
Download: ML20049J161 (4)

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NUCLEAR REGULATORY COMMISSION E'

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L cal PDR March 8, 1982 ORB Reading NSIC Docket No. 50-409 DCrutchfield L505-82-03-041

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DDudley 0 ELD 0.I&E Mr. Frank Linder ACRS (10)

General Manager SEPB Dairyland Power Cooperative DChaney 2615 East Avenue South GJohnson La Crosse, Wisconsin 54601

SUBJECT:

INSERVICE INSPECTION REVIEW - LA CROSSE BOILING WATER REACTOR The NRC and its contractor have begun to review y6ur submittals regarding the inservice inspection relief requests at the La Crosse plant.

Prelimi-nary results indicate that additional informatio'nis needed before the review can be completed.

This information is described in the enclosure.

Please provide this information within 30 days of the date of'this letter.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore OMB clearance is not required under P.L.96-511.

Sincerely, 4 04 Dennis M. Crutchfiel Chief Operating Reactors Branch #5 Division of Licensing

Enclosure:

Request for Additional Information cc w/ enclosure:

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2-March 8, 1982 Mr. Frank Linder

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Fritz Schubert, Esquire U. S. Environmental Protection Staff Attorney Agency Dairyland Power Cooperative Federal Activities Branch 2615 East Avenue South Region V Office La Crosse, Wisconsin 54601 ATTN:

Regional Radiation Representative 230 South Dearborn Street

0. S. Heistand, Jr., Esquire Chicago, Illinois 60604 Morgan, Lewis & Bockfus 1800 M Street, N. W.

Mr. John H. Buck Washington, D. C.

20036 Atomic Safety and LicerP ng Appeal Board U. S. Nuclear Regulatory Commission Mr. R. E. Shimshak Washington, D. ^

20555 La Crosse Boiling Water Reactor Dairyland Power Cooperative Dr. Lawrence R. Quarles P. O. Box 135 Kendal at Longwood, Apt. 51 Genoa, Wisconsin 54632 Kenneth Square, Pennsylvania 19348 Ms. Anne K, Morse Charles echhoefer, Esq., Chairman

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Coulee Region Energy Coalition Atomic Safety and Licensing Board P. O. Box 1583 U. S. Nuclear Regulatory Commission La Crosse, Wisconsin 54601 Washington, D. C.

20555 La Crosse Public Library Dr. George C. Anderson 800 Main Street Department of Oceanography La Crosse, Wisconsin 54601 University of Washington Seattle, Washington 98195 U. S. Nuclear Regulatory Commission Resident Inspectors Office Mr. Ralph S. Decker Rural Ro'ute #1, Box 276 Route 4, Box 1900 Genoa, Wisconsin 54632 Cambridge, Maryland 21613 Town Chairman Thomas S. Moore Town of Genoa Atomic Safety and Licensing Appeal Board Route 1 U. S. Nuclear Regulatory Commission Genoa, Wisconsin 54632 Washington, D. C.

20555 Chairman, Public Service Commission Mr. George R. Nygaard of Wisconsin Coulee Region Energy Coalition n,

Hill Farms State Office Building 2307 East Avenue Madison, Wisconsin 53702 Lacrosse, Wisconsin 54601 N

Alan S. Rosenthal, Esq., Chairman James G. Keppler, Regional Administrator Atomic Safety and Licensing Appeal Board Nuclear Regulatory, Commission, Region III U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement Washington, D. C.

20555 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Frederick Milton 01sen, III 609 North lith Street Lacrosse, Wisconsin 54601

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i REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM' Lacrosse 3

1.

Bl.1 (B-A) (pg'1, Ref.1). Reactor vessel longitudinal and circumferential welds in core region

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Bl.2 (B-B) (pg 1, Ref.1). React 5r vessel-longitudinal and circumferential welds not in core region These requests for relief from the requirements of Ref. 2 concern volumetric examination of the above pressure-retaining welds.in the reactor vessel. Access to these welds is prevented by a concrets shield wall around th'e vessel.

The following additional information is requested:

4 (a) Identify the portions of any welds which might be accessible for volu.

metric examination from inside the vessel'or from the outside because of their proximity to any' access ports or"6ther penetrations in the concrete shield.

(b) Is there access to perform surface or remote visual examinations on any of these welds to supplement volumetric examinations? Please provide an estimate of the percentage of. each weld which may be accessible for these supplementary examinations.

2.

Bl.4 (B-D) (pg 2, Ref.1). Reactor vessel recirculation nozzles #1;2,5,6; vessel to nozzle welds and inside radius sections Relief is requested from performing the required volumetric examinations on _ the above areas in reactor vessel nozzles.

Radiation levels over 1 R/hr would result in high exposures to person.nel in performance of t,hese examinations.

the following additional information is requested:

(a) is there access to perfo'm remote visual examinations on an of the r

requirdd areas?

Please provide an estimate of the p.erce6tage of each weld or inside radius section which may be accessible for remote visual examination.

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.3.

Bl.5 (B-E) (pg 2, Ref.1). CRD and liquid level penetration welds This request for relief applies to visual inspection of the above welds.

These ' partial penetration welds are inside the 'reictor. vessel and are not.

accessible from the outside.

The following additional information is requested:

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(a) Have you considered remott visual examinations o.f these w' lds? ' Please e

detail the degree of access to these welds for remote visual examination from the inside of the vessel during refueling.

4.

Bl.14 (B-I-1-) (pg 3, Ref.1). Reactor vessel cladding

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Relief is requested from visual inspection of reactor vessel cladding because of high radiation levels. A more recent edition of the code (Ref. 3) has eliminated the requirement to perform the catbgory B-I-1 inspections.

Have you considered removing this inspection., as we.ll as the Bl.13 (B-I-1)

. inspection, from your program?

5.

B4.1 (B-F) (pg 3, Ref. 1). 22BC, 2-in. branch connection on 20-in. loop suction (loop lb)

Relief i! requested from performing a volumetric examination of this 2-inch socket weld due to improper configuration.

It is not stated if an alternative

. surface examiration will be performed on this weld.

Please clarify your position.

1 6.

General. Ref. 1 Requests A number of requests for relief cite high radiation fields as deterrents to performing required examinations.

Please-provide an estimate of total exposure dich would result for each of these items.

REFERENCES:

l 1.

Table of Requests for Relief for Class I components in DPC letter, LAC-7025, dated 7/14/80.

2.

ASME Boiler and Pressure Vessel Code,Section XI, Div.1,1974 Edition, with addenda through Summer 1975, i

3.

ASME Boiler and Pressure Vessel Code,Section XI, Div.1,1977 Edition, i

l with addenda through Summer 1978, t

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