ML20213D923
| ML20213D923 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 11/05/1981 |
| From: | Johnston W Office of Nuclear Reactor Regulation |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0423, CON-WNP-423 NUDOCS 8112020771 | |
| Download: ML20213D923 (3) | |
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.A 7.1 Docket !:o. : 50-397
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I:El10RAf!DUi1 FOR: Robert L. Tedesco, Assistant Director
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Willian V. Johnston, Assistant Director for fiaterials & Qualifications Engineering Division of Engineering
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SUBJECT:
UASHINGT0t' PUDLIC POWER SUPPLY SYSTE!:, UPPS i:UCLEAR PROJECT, U: IT 2 (OL) DOCKET l'U :BER 50-3E7 Plant Name: UPPS i:uclear Project Unit l'o.2 Suppliers: Ceneral Electric; Curns and P,oe Licensino Stace: OL-SEF:
Docket !!o.: 50-307 Responsible branch and Project ::anager: LB f 2; P.. Auloc!:
Reviewer:
D. Turovlin Status of Review: Draft SER for Section 1.1.2 " Spent Fuel Storage."
The Corrosion Ennineering Section of the Chemical Engineering Cranch, Division of Engineering, has reviewed FSAR Section 9.1.2 " Spent Fuel Storage."
Based upon our evaluation, we find that the naterials of construction of the framework of the spent fuel storage rack are compatible with the fluids in spent fuel pool and are therefore acceptable. However, the neutron poisen naterial to be used in these racks is the same as that used in the Kewaunee racks, and that plant has experienced off-gasing probler.s. The applicant is currently evaluating the problem. We will conplete our evaluation of this iten after we receive additional infornation.
Our section of the Safety Evaluation Report is enclosed.
Uillian V. Johnston, Assistant Director for fiaterials & Qualifications Engineering Division of Engineering
Enclosure:
As stated
Contact:
B Turovlin DISTRIBUTION:
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W A S HI tJ G T 0 tJ PUBLIC POWER SUPPLY SYSTEM WPPS tJUCLEAR PROJECT, UfJIT No. 2 CHEMICAL EtlG IflE E R IN G B R Af4 C H 9.1.2 Spent Fuel Storage Nuclear reactor plants include storage facilities for the wet storage of spent fuel assemblies.
The safety function of the spent fuel pool and storage racks is to maintain s
the spent fuel assemblies in a suberit/ cal array during alL credible storage conditions.
We have reviewed the compatibility and chemical stability of the materials (except the fuel assemblies) wetted by the pool water.
In addition, our review has included an evaluation of the Tetrabor neutron' absorber material used in the[high density storage locations for environmental stability.
The high density spent fuel storage racks are of welded 2
stainless steel construction with a neutron absorber (Tetrabor) sandwiched between stainless steel sheets.
Tetrabor is composed of. particles of boron carbide in a carbon matrix.
This is the same neutron absorber (poison) material that is used in the Kewaunee spent fuel pool storage racks.
The Kewaunee spent fuel pool racks have experienced outgassing and cett rack swelling probtems.
The applicant is evaluating some proposed methods to re' solve this problem.
The applicant has committed to provide us with additional information on this issue.
The pool liner, rack Lattice structure and the high
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In this environment of oxygen-saturated high purity water, the corrosive deterioration of the type 304 stainless steel
-5 should not exceed a depth of 6.00 X 10 inches in 100 years, which is negligible relative to the initial thickness.
Dissimilar metal contact corrosion (galvanic attack) between the stainles) steet of the pool liners rack Lattice structurer fuel storage tubes, and the Inconel and the Zircatoy in the spent fuel assemblies wilL not be significant because atL of these materials are protect,ed by highly passivating oxide films and are therefore at similar potentials.
We wilL report on the resolution of the neutron absorber material in a subsequent safety evaluation report.
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Docket flo. 50-397
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Washington Public Power Sdp)jds.,f (WPPSS)
APPLICAflT:
tpa-FACILITY:
WPPSS fluclear Project !!o. 2
SUBJECT:
SUMMARY
OF OCTOBER 19-21, 1981 CASELOAD FORECAST PAriEL lEETIfiG AfiD SITE VISIT
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The applicant held meetings with the representatives of flRC's Caseload Forecast Panel at the site of the Washington Public Power Supply Systen's fiuclear Project tio. 2.
The meeting agenda and the list of attendees are attached.
On October 19, 1981, the applicant described the progress of engineering and construction at the W!iP-2 site. As of Septenber 30, 1931, installation of largg piping was 96% complete, large pipe welds and large pipe valves were 92% complete, large pipe hangers 89% and small pipe was 89% complete. All the cable trays. ere inpplace but only 63% of cables were pulled and 62% were terminated.
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The Drywell and the Containment are on the critical path for project completion.
In the drywell our major concerns were in completing the sacrifical shield wall repair (about 400 voids to be filled), mechancial and electrical work, work associated with the installation of pipe whip restraints and large bore piping.
In the reactor building there is a delay in the start of the nachanical work.
During our site visit on October 20, 1931, we observed very little mechanical work being done with the exception of the ongoing work in the wetwell area.
Conclusions The applicant is currently behind schedule in systems turnover and any delay in pre-operational testing will impact the plant completion schedule. Based on the status of construction at this time, the f!RC Panel projected a February 19M fuel load date for utiP-2 (5 months delay). We were also informed that the Supply System is evaluating different means to recover the schedule.
R. Auluck, Project !!anager 0 Licensing Sranch !!o. 2 Division of Licensing
Enclosures:
1.
fleeting Agenda 2.
List of Attendees a
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