IR 05000409/1986014
| ML20213E028 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 11/07/1986 |
| From: | Danielson D, Norton J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20213D992 | List: |
| References | |
| 50-409-86-14, IEB-79-02, IEB-79-2, NUDOCS 8611120375 | |
| Download: ML20213E028 (3) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No: 60-409/86014(DRS)
Docket No: 50-409 License No: DPR-45 Licensee:
Dairyland Power Cooperative 2615 East Avenue - South Lacrosse, Wisconsin 54601 Facility Name: Lacrosse Boiler Water Reactor Inspection At: Lacrosse Site, Genoa, WI Inspection Conducted: October 27-30, 1986 3.:8. M
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Inspector:
J. F. Norton 11/1/%
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Date W
l')7)f6 Approved By:
D. H. Danielson, Chief
_Date Materials & Processes Section In_sppct_i_on Summary Areas Inspected?~RFutiiie announced inspectWnTf"the resoluti)o)n~ of Inspection on October ~27-30,1986(R_eportNo. 50-409/86014(DRS TEliiilletin No. 79-02 " Pipe Support Baseplate Design Using Concrete Expansion
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Anchors (25528).
Results: No violations or deviations were identified.
8611120375 861107 PDR ADOCK 05000409
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it DETAILS 1.
_ Persons Contacted Dairyland Powe_r, C_ooperative _(D_P_CJ
- J. Parkyn, Plant Superintendent
- R. Wery,- Quality Assurance Supervisor P. Sampson, ISI Engineer P. Shafer, Radiation Protection Engineer
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L_S. Nu_glear Regulatory Conrnission (NRC)
I. Villalva, Senior Resident Inspector
- Denotes those persons attending the exit interview.
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Licensee Action on IE_ Bulletins
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(Closed)
IE Bulletin No. 79-02(409/79-02-BB;IB;2B;3B):
IE Bulletin No. 79-02 " Pipe Support Baseplate Design Using Concrete Expansion Anchors (25528)."
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General
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IE Bulletin 79-02 addresses the design and construction of pipe support baseplates with concrete expansion anchors. The bulletin was issued March 3,1979, and supplemental revisions were issued July 21, August 20, and November 8, 1979. The primary purpose of the bulletin was to assure that licensees had appropriately
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considered baseplate flexibility and its potential effects on anchor loads.
b.
Program Directives and Reco_r_ds The NRC inspector reviewed the following:
DPC Letter, Linder to Keppler, LAC-6483, dated August 23, 1979.
- DPC Letter, Linder to Keppler, LAC-6602, dated October 24, 1979.
- l DPC Letter, Linder to Keppler, LAC-6704, dated December 20, 1979.
L LACBWR Facility Design Change Proposals.
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LACBWR Facility Design Change Orders.
- IE Bulletin 79-02, " Baseplate Design Calculations, Nuclear
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-Engineering Services Incorporated, dated January 30, 1984.
Mill Certificates for Material Stock.
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Welding Data Summary Sheets.
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Magnetic Particle Examination Sheets.
c.
Baseplate Design Sargent and Lundy (58L) designed the original pipe support baseplates for the plant. The Lacrosse Boiling Water Reactor (LACBWR) is an older facility where Seismic Category I requirements did not exist i
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at the time of licensing, nor did the Safeguards Report for Operating
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Authorization (FSAR)definesafety-relatedsystems. Thus, S&L did not retain their design calculations. The licensee surveyed the plant pipe support installations and identified those applicable to IE Bulletin 79-02.
d.
Baseplate Re-Desig The licensee decided-to re-design and replace all pipe support installations governed by IE Bulletin 79-02. The re-design was accomplished by Nuclear Energy Services Incorporated. The replacement of all support plates has been completed.
e.
Conclusion Baseplate replacenent was accomplished on all installations to assure compliance with actions set forth in IE Bulletin 79-02. The changes were accomplished in accordance with licensee engineering and QA/QC requirements. The NRC inspector reviewed the QC documentation.
Also, several of the installation were inspected in the company of an In Service Inspection Engineer. All program directives, and.
engineering and QC documentation were found to appropriately address the Bulletin issues. No discrepancies between design drawings and construction were discerned. Based on the aforementioned data, it is concluded that IE Bulletin No. 79-02 has been fully implemented at the Lacrosse Boiling Water Reactor Plant. No violations or deviations were identified.
3.
Exit Meeting The inspector met with licensee representatives (denoted under Persons Contacted) on October 30, 1986. The inspector sumarized the purpose and findings of the inspection. The licensee acknowledged the findings as reported herein. The inspector also discussed the likely informational content of the inspector's report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any such documents / processes as proprietary.
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