IR 05000508/1981013
| ML20031A526 | |
| Person / Time | |
|---|---|
| Site: | Satsop |
| Issue date: | 09/03/1981 |
| From: | Albert W, Bishop T, Dodds R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20031A523 | List: |
| References | |
| 50-508-81-13, 50-509-81-13, NUDOCS 8109230627 | |
| Download: ML20031A526 (4) | |
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U. S. NUCLEAR REGUIAIORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
50-508/81-13 Report No.
50-509/81-13 Docket No.
50-508, 50-509 License No.
CPPR-154,155 Safeguards Group Licensee:
Washington Public Power Supply System P. 0. Box 1223 Elma, Washington 98541 WNP 3-5 Facility Name:
Site Inspection at:
Inspection con d. nJu)y 2A3l, lyl,y y[
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Inspector j
j g K GC Albert, Sen%f Ref1 dent Espector Date Signed g ItIhLp 9/s/ai
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T. W. Bishop, Uhief, Reactor Projects dection 1 Date Signed Date Signed Approved By:
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R. T. Dodds, Chlef, Reactor Projects Section 2, Date Signed Reactor Construction Project Branch Sut:rnary:
Inspection during the period of July 24-28, 1981, Report Nos. 50-508/81-13 and 50-509/81-13-Areas Inspected:
Routine unnnnounced inspection by regional based inspectors of construction activities including licensee's disposition and corrective action s'
'with regard to a significant lack of concrete consolidation in a shear wall and licensee's system for controlling open NRC items.
The inspection involved 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> on site by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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8109230627 810904 s PDR ADOCK 05000508; RV Form 219 (2)
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1-DETAILS.
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- Persons Contacted
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Washington Public Power Supply System (Supply Systeml
- R. S. Leddick, Program Director WNP 3-5
- 0. E. Trapp, Quality Assurance Manager
- J. Puzauskas, QA Supervisor
- *D. E._ Dobson, Project Manager WNP 3-5 E. Stephens, QA Engineer D. Kerlee, QA Audits Supervisor b.
Ebasco Services Inc. (Ebasco)
- A.M.Cutrona,QualityAssuranceMahager R. G. Peck, QA Engineer
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Morrison-Knudsen i(MK).
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D. Reed, Project Manager-t
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R. Davis, Quality Manager >
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- Denotes those also attending' the fjrst NRC exit meeting on July 31, 1981.
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' Plant Tours
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Tours of both~ units were made. Noitemsjofinoncompliance.were.noted.
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3.
0 pen Item Control l
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The. licensee's system for controlli.ng open items g'enerated' by USNRC reports was examined.
The' inspector had.no-further questions.. However, it should be noted that the system examined is used only to control.open items from the USNRC inspection reports.
Items arising from other sources such as Bulletins, Circulars and.Information Notices, are controlled by another system.
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Safety Related Structure'-' Unit 3
- At the start of the inspection-a meeting was neld with the licensee,
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the A-E and the contractor for civil worklin.the Reactor Auxiliary-Building, the Morrison-Knudson Company.
The purpose of the meeting
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This placement also included a portion of the same' wall'which extended
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j into the north control room HVAC area.- (Placement No. ABW 19 and 21,
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428).
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At the initial meeting the contractor stated that the cause o' the discrepent condition was a ' combination of conditions all of which were within specifications, but. which were of such values that placement was very difficult; this coupled with..the accidental but temporary entrapment of some vibrators ;in the rebar. mesh during. blacement resulted
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in extremely poor consolidation.
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The NRC position was_that the conditions should h' ave $een recognized at the start of the placement and that consequently some~ corrective action to the quality control system'wastindicated.
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s The NRC also expressed concern about theid,isposition of the nonconforming wall.
The voids resulting sfrom the poor consolidatiori'of concrete were such that the structural integ'ri_ty'of the wall,was obviously affected, therefore normal concrete repair procedures did not appear
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adequate.
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An examination of the wall and associated documentation was made by the NRC inspectors.
The -following was detennined:
Voids existed over 25% of the surface of the placement. The
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depth of voids ~were generally limited to 12" altnough some penetrated entirely through the 42" wall where pipe chases existed.
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The total volume of the voids was calculated by the NRC to be
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approximately 14 cu yards.
This volume is based on measurements made after most of the unsound concrete had been chipped out.
The placement utilized 117 cu yards 'of concrete.
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All the concrete exposed after chipping appeared sound although
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investigation of.the through-wall voids still remained to be done after removal of the pipe chases associated with these voids.
Chipping had caused some rebar damage.
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A second meeting was held with the licensee in which it was confirmed that a report in accordance with 50.55(e) would be submitted.
Further the licensee stated that a specific repair procedure would be developed for the wall.
The inspectors examined a corresponding wall on the south side of the plant which had been placed subsequently. Consolidation of the concrete in this wall appeared satisfactory.
This item will be further examined as follcwup to the 50.55(e) report (50-508/81-07-29)
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Exit Meeting At-the exit interview, the inspectors confirmed the un' erstandings d
reached concerning reporting and repair procedure development.
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item will remain open.
b Of the-individuals contracted, those designated by an asterisk in section.l.
also attended the exit interview.
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