IR 05000282/1981014
| ML20031H303 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island |
| Issue date: | 10/07/1981 |
| From: | Hawkins F, Landsman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20031H292 | List: |
| References | |
| 50-282-81-14, 50-306-81-17, IEB-80-11, NUDOCS 8110270342 | |
| Download: ML20031H303 (3) | |
Text
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., U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III- . Report No. 50-282/81-14; 50-306/81 17 Docket No. 50-282; 50-306 License No. DPR-42; DPR-60 Licensee: Northern States Power Company.
414 Nicollet Mall hinneapolis, MN 55401 Facility Name: Prairie Island Nuclear Generating Plant Units 1 & 2 Inspection At:. Red Wing, MN Inspection Conducted: April 23 and July 15, 1981.
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- /C!I ! Inspectors: R. B. Landsman e& WUb-for: I' Approved By: F. C. Hawkins, Acting Chief /p[7[ W ' Plant Systems Section Inspection Summary Inspection on April 23 and July 15, 1981, (Report No. 50-282/81-14; 50-306/81-17) Areas Inspected: Licensee action relative to Bulletin No. 80-11, " Masonry Wall Design." The inspection involved a total of 16 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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.. _- .. - . . . DETAILS Persons Contacted ' Licensee (NSP) G. Goering, General Superintendent, Nuclear Technical Services P. Johnson, Supervising Civil Engineer C. Baltos,. Engineer Flour , W. Stern, Engineer } R. Smith, Engineer J. Khanna, Engineer U.S. N.R.C, Region III B. Burgess, Resident Inspector Licensee Action on IE Bulletin No. 80-11 The NSP response to IE Bulleting No. 80-11, " Masonry Wall Design," which
required a re-evaluation of constructed masonry bock walls, was reviewed as follows: 1.
Identification ! All areas were surveyed to identify masonry walls which were in proximity to or have attachments from safety-related piping or , equipment such that wall failure could have affected a safety-re- ' lated system. Two survey teams were used.
They consisted of one i member from each of the electrical, instrumentation and controls, t mechanical and structural disciplines. This investigation indicated j that 121 walls were subject to Bulletin requirements. The teams ! prepared detailed " wall maps" which identified the locations of l systems or components which contribute loads to the masonry walls.
The licensee's July 8, 1980 submitta? which tabulated all walls and attachments was reviewed.
It was found to be inaccurate, in that some component descriptions were in error and certain component were left off the lists.
It was subsequently determined by the Region III inspector that the wall maps used by the design engineer for the required re-evaluations were accurate. The subject lists were pre-l liminary and had no impact on the re-evaluation performance. The j licensee indicated that revised lists were being made and would be I submitted to provide the NRC with accurate documentation. This item l remains open pending review of the licensee's submittal (282/81-14-01; ! 306/81-17-01).
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. , 2.
Re-evaluation Priority The licensee set up an appropriate priority program as follows: First: Walls which affect systems required to bring the plant to a safe shutdown or to maintain it in the safe shutdown condition.
Second: Walls which affect systems associated with the safety of plant personnel.
Third: Walls which affect all other safety Class I systems.
Within each of these categories, walls were also prioritized in the following order: First: Walls with highest number of safety systems attached.
Second: Walls with highest loads.
3.
Wall Function and Construction Walls at P.I. were designed as partition wall or as shield walls.
The licensee has adequately described the construction details of the walls. Adequate inspection and quality control measures were taken at the time of construction to insure that no significant weaknesses were permitted.
4.
Engineering Re-evaluation The re-evaluation determined that 28 walls did not meet the new design criteria. Each wall has been modified and the effected repairs were observed to be installed accordingly. The repairs were accomplished under Design Change Package No. 80L624.
Each , package consisted of: a.
List of affected drawings b.
Detailed design description c.
Safety evaluation d.
Installation (work) procedures e.
Fire protection f.
Radiation exposure g.
Work request authorization 5.
Exit Meeting The inspector met with licensee representatives (denoted under Persons Contacted) at the conclusion of the inspection on July 15, 1981. The inspector summarized the purpose and findings of the inspection. The licensee acknowledged the findings reported herein.
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