IR 05000409/1978012
| ML19267A292 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 11/27/1978 |
| From: | Danielson D, Yin I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19263A935 | List: |
| References | |
| 50-409-78-12, NUDOCS 7901040006 | |
| Download: ML19267A292 (3) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-409/78-12 Docket No. 50-409 License No. DPR-45 Licensee: Dairyland Power Cooperative 2615 East Avenue La Crosse, WI 54601 Facility Name:
La Crosse Boiling Water Reactor
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Inspection At: La Crosse Boiling Water Reactor Site, Genoa, WI Inspection Conducted: November 1, 1978 Inspector:
1. T. Yin y-
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Approved By:
D. H. Danielson, Chief
// J5 7)! 2 7J Engineering Support Section 2
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Inspection Sunac :'
Inspection on November 1, 1978 (Repor* No. 50-409/78-12)
Areas Inspected: Discusssions with th. licensee in the areas of system seismic upgrading; review of stress calculations on some of
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the essential pipe systems. The inspection involved a total of three inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviation were identified.
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7901040006
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DETAILS Persons Contacted Principal Licensee Emplovee
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R. E. Shimshak, Plant Superintendent Functional or Program Areas Inspected 1.
General J
As of present, there are no snubbers.? stalled on the piping or equipment in the plant for protection against possible seismic or other dynamic transient loadings. Since 1974 the licensee has been in the process of applying for conversion of their provisional operating license to a full term operating license. To do this, one of the require-ments is to upgrade the structural and mechanical analyses to include seismic considerations, and to modify the existing systems, where required, as a result of the evaluation. At the present time, the licensee is in discussions with NRC-NRR to determine (1) what equipment, building, or systems are considered essential that require seismic analyses, (2) acceptable methology for doing the analyses, and
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(3) schedules for plant modification if any are
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necessary.
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Review of Stress Calculations During one of the meetings between the licensee and the NRC-NRR staff on August 8, 1978, the siesmic studies of the site and related structural response spectra was discussed, and sub-sequently several stress analyses on major piping systems
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within the containment were submitted by the licensee as
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examples of analytical work already accomplished. The analyses which are listed below, were reviewed by the inspector for the purpose of future site observations. The stress analysis reports were prepared by Nuclear Energy Services Inc., (NES) of Danbury, Connecticut. The calculations were performed in accordance with the design requirements for Class 2 piping components of the ASMI,Section III, Division I, " Nuclear Power Plant Components," 1974 Edition.
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NES 81A0087, " Seismic and Stress Analysis of LACBWR
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Feedwater Piping System," dated June 18, 1975.
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The analysis indicated that eleven (11) snubbers, four (4) rigid restraints, and some elastic restraints will be added to the system, b.
NES 81A0088, " Seismic and Stress Analysis of LACBWR Main Stream Piping System," dated August 1, 1975.
The analysis indicated that four (4) snubbers, two (2)
rigid restraints, and some elastic restraints will be added to the system.
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NES BLA0089, " Seismic and Stress Analysis of LACBWR Recirculation Piping System," dated November 17, 1975.
The analysis indi.cated that four (4) snubbers will be added to Loop A pump and motor, and four (4) snubbers will be added to Loop B pump and motor.
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NES BlA0090, " Seismic and Stress Analysis of the LACBWR High Pressure Core Spray Suction Line Piping System,"
dated July 9, 1976.
The analysis indicated that only elastic restraints will be addeI to the system.
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NES 81A0091, " Seismic and Stress Analysis of the LACBWR High Pressure Core Spray Discharge Line Piping System,"
dated May 10, 1977.
The analysis indicated that seven (7) sets of rigid restraints will be added to the system.
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Snubber Discussion
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The licensee is evaluating the possibility of acquiring snubbers for the piping components. The inspector had discussions with the Plant Superintendent relative to snubber installation and surveillance requirements, and also nuclear power plant snubber problems encountered in the past.
Exit Interview The inspector met with the Plant Superintendent at the conclusion of the inspection on November 1, 1978.
The inspector summarized the purpose of the inspection and discussed some QA/QC require-ments relative to the snubber installations.
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