IR 05000409/1986018

Insp Rept 50-409/86-18 on 861217 & 30.Violation Noted: Failure of Engineering to Review Support Design Changes

ML20197D012
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	01/21/1987
From:	Danielson D, Yin I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20197D003	List: IR 05000409/1986018 ML20197D000 ML20197D007
References
50-409-86-18, IEB-79-14, NUDOCS 8702020154
Download: ML20197D012 (5)

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U.S. NUCLEAR REGULATORY COMMISSION

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REGION III

Report No. 50-409/86018(DRS)

Docket No. 50-409 License No. DPR-45 Licensee: Dairyland Pcwer Cooperative 2615 East Avenue - South La Crosse, WI 54601 Facility Narr.e: La Crosse Boiler Water Reactor Inspection At: La Crosse Site, Genca, Wisconsin Inspection Conducted: December 17 and 30, 1986 Inspector- sa T. Yin #!2/k/

Date Approved By: D. H. Danielson, Chief //2s /r7 Materials and Processes Section Date

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Insp_ection Sumary Inspection on December 17 and 30,1986 (Report N ~

Areas Inspe'ct'ed: SpeciB unanncunced inspection of -50 the409/_86018(DRS))

resFuTion of IE Bulletin No. 79-14, " Seismic Analyses for As-Built Safety-Related Piping Systems" (25529).

Results: Within the area inspected, one apparent violaticn was identified (Failure of engineering to review support design changes - Paragraph 3.d).

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DETAILS 1. Persons Contacted DairylandPowerCooperative(D_PCl

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• J. Parkyn, Plant Superintendent

• R. Wery, Quality Assurance Supervisor H. A. Towsley, Consultant

• D. Thorpe, Mechanical Design Engineer L. Goodman, Operations Engineer D. L. Rybarik, Mechanical Engineer U.S. tiuclear Reculato_ry Ccamission Region III (RIII)

I. Villaiva, Senior Resident Inspector

• Denotes those attending the exit interview on December 30, 198 . Licensee Action on IE Bulletins (Closed) IE Bulletin No. 79-14 (409/79-14-BB; 409/79-14-1B; 409/79-14-2B; 409/79-14-3B;): " Seismic Analysis for As-Built Safety-Related Piping Systems," July 2, 1979; Revision 1, July 18, 1979; Supplement 1, August 15, 1979; and Supplement 2, Septen.ber 7,1979. See Paragraph 3 for detail . Followup cn IEB 79-14 Scope As part of the Systematic Evaluation Program (SEP), in February 1977 the isRC initiated a review for the design of LACBWR. This review was conducted to provide (1) an assessment of how LACBWR complies with the then current safety issues; (2) resolution of any differences in an integrated effort, and (3) a documented evaluation of plant safety. In the area of seismic evaluation, it was determined that piping systems needed upgrading in the following areas:

Install overhead storage tank (0HST) and shutdown condenser cross connection make-up pipin Install condenser make-up line from the containment to the CHS *

Modify the existing alternate core spray pipin Add rigid restraints to the high pressure core spray (HPCS)

piping syste m

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b. Document Review The NRC inspector reviewed the pertinent documents and related correspondence regarding the seismic upgrade including:

DPC letter to RIII, "IE Bulletin No. 79-14 Seismic Analyses for As-Built Safety-Related Piping System," September 5,197 OPC letter to RIII, " Reportable Occurrence No. 82-05,"

April 14,1982, reporting discrepancy discovered during walkdown evaluation of HPCS discharge piping analysi *

DPC letter to RIII, " Reportable Occurrence No. 82-05,"

April 26,1982, reporting evaluation of seismic analysis discrepanc NRC NUREG-0827, " Integrated Plant Safety Assessment - Systematic Evaluation Program for La Crosse Boiling Water Reactor,"

June 1983, Section 4.13, " Topic III-6, Seismic Design Considerations."

DPR Letter No. LAC-10251 to NRC-NRR, October 11, 1984, providing results of Sandia National Laboratories studies per NUREG-082 DPR Letter flo. LAC-10639 to NRC-NRR, March 15, 1985, providing DPR answers to NRC SEP question DPR Letter No. LAC-10933 to NRC-NRR, June 3, 1985, transmitting HPCS piping seismic and stress analyses fcr NRC staff revie NRC Letter to CFR, " Integrated Consequence Study," September 8, 1986, providing the NRR report, " Safety Evaluation by the Office of Nuclear Reactor Regulation Relating to NUREG-0827 Sections 4.6, 4.9, and 4.13 Integrated Consequence Study," and requesting a schedule for completion of the remaining engineering, analyses, and implementation of necessary plant modification *

DPR Letter No. LA.C-12001 to hRC-NRR, December 11, 1986, providing a tentati"2 schedule for systems evaluations and upgradin c. Review of HPCS Seismic Modification Documents The hRC inspector reviewed the following documents and had no adverse coments:

Nuclear Energy Services, Inc. (NES) Report No. 81A 0042, "High Pressure Core Spray Suction and Discharge Pipe Supports for the Lacrosse Boiling Water Reactor," Revision 4, March 22,198 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _

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i LACBWR Facility Change Proposal Ho. 53-80-2, "High Pressure Core Spray Suction and Discharge," closed on November 7, 1980, and associated Maintenance Request showing scope and work performanc d. Walkdcwn Inspection

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The NRC inspector verified the following: -

(1) _ Piping Dimensicn Verification

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The inspection was based on piping isemetric drawings shown on Figure 2-1, "HPCS Discharge Line," and Figure 2-2, "HPCS Suction Line," of the Structural Mechanics Associates Report No. SMA-CT 30001.01R01, " Seismic and Stress Analysis of High Pressure Core Spray Suction Line Piping System," February 198 Of the eight pipe segments measured, six were verified to be correct. Two as-built support location dimensions near Support No. HP-1 deviated from design as follows:

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Design Measured 3'-6" 5'-4" >

4'-6" 2'-8" Also, many as-built rigid restraints were shown as spring

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supports on the stress isometric drawings. Subsequent review identified that these restraints were mcdeled with sufficiently high stiffness so they could be considered rigid. The NRC inspector considers this practice to be acceptabl (2) Pipe Supp_o_rt Configuration Verification

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l The following supports were inspected:

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_ Support N Findings 6 HP-1 Pipe was not supported inside the bracket. Corrective action was taken

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by DPC prior to the conclusion of the

NRC inspectio A pipe support not accounted for in the stress report was observed attached to the main support steel structure.

i 345 A din:ension on a W6 x 15 nain steel

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member deviated from design (4'-6 3/4" design; 4'-2 5/8" measured).

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