IR 05000382/1979010
| ML19254D439 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 09/11/1979 |
| From: | Randy Hall, Stewart R, Tapia J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19254D437 | List: |
| References | |
| 50-382-79-10, NUDOCS 7910250524 | |
| Download: ML19254D439 (5) | |
Text
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-382/79-10 Docket No. 50-382 Category A2 Licensee: Louisiana Power and Light Company 142 Delaronde Street New Oricans, Louisiana 70174 Faci' ty Name: Waterford Steam Electric Station, Unit No. 3 Inspection at: Waterford Site, Taft, Louisiana Inspection conducted: August 15-17 and 21-24,1979 C'
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Inspectors:
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3-ll ~79 R. C. Stewart,7hactor I'nspector, Projects Section Date (Paragraphs 1, 2, 3, 4 & 6)
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his R-l \\ ~l9 J. I(. JTapia, Read or Inspector, Engineering Support Date SeMion (Paragraph 5) (August 21-24, 1979, only)
Approved:
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W. X. Crossman, Chief, Projects Section Dale
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n R. E. Hal(, Chief, Engineerit(g Support Section D(te
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Inspection Summary:
Inspection on August 15-17 and 21-24, 1979 (Report No. 50-382/79-10)
Areas Inspected: Routine, unannounced inspection of construction activities including observation of work related to concrete placement for the Reactor Building shield wall and dote; follow-up review of previously identified inspection findings; and a review of the job site ASME Code certification status. The inspection involved seventy-five inspector-hours by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Principal Licensee Personnel
- T. F. Gerrets, QA Manager C. Dechreaux, Project Coordinator
- J. Woods, QA Engineer
- S. A. Alleman, Assistant Station Superintendent
- B. P. Brown, QA Engineer T. K. Armington, S/V Engineer
- B. M. Toups, QA Engineer Technician Other Personnel
- J. Crnich, Site Manager, Ebasco, Inc.
- R. Fulhiser. Project Superintendent, Ebasco, Inc.
J. Gutierrez. Site QA Engineer, Ebasco Inc.
G. Warren, QA Engineer, Fegles-Power Service Corp.
- J. Ransom, Project Superintendent, Fegles-Power Service Corp.
- De ces those attending the exit interview.
The IE inspectors also interviewed other licensee and contractor personnel including mechers of the engineering and QA/QC stef fs.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (50-382/79-09): Material Storage Control Verifi-cation.
During this inspection, the IE inspector conducted a follow-up review and verification of the storage yard caterial control. The IE inspector verified that the temporary pipe hanger tie-rods were identified and removed from tS-
% rbine Building.
In addition, the IE inspector observed that a locked chain link fence has been installed around the area designated as " surplus material." This matter is considered closed.
(Closed) Reported Part 21: Mechanical Draft Wet Cooling Towers.
In a letter dated lby 3,1979, the wet cooling water supplier expressed a concern regarding the capability of the essential cooling water system to provide the required heat dissipation duty under the required operating, accident and shutdown modes and design conditions.
During this inspection, the IE inspector revicwed the licensee's A/E and supplier correspondence file regarding this matter.
There is no evidence that would indicate that the wet cooling towers do not meet the purchase specifications required by the licensee's A/E.
In addition, a functional capability performance test-2-1209 350
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in accordance with ASME Power Test Code for Atmospheric Water Cooling Equipment, PTC-23-1958, is to be performed during the plant pre-operational testing phase and is scheduled to be performed during that portion of the hot functional testing. The licensee's pre-operation test, SFG-36-003, prescribes the guaranteed performance requirements. This matter is con-sidered resolved.
(Closed) Unresolved Item- (50-382/79-06): Design Change-Separation Criteria.
During a previous inspection, the IE inspector requested additional infor-mation relative to a design change (DCN-NY-E-231-1) authorizing a one-eighth inch blanket of Quelpyre Mastic, Type 703B, in lieu of the required one inch free air space between crossing raceways. During this inspection, the licensee provided the IE inspector a copy of correspondence from the supplier, Quelcor, Inc., dated June 18, 1979, identifying the specific tests conducted, in accordance with IEEE 384, which support the design change. This matter is considered resolved.
(Closed) Unresolved Item (50-382/79-08): Curing Concrete Test Specimens-Water Tank Temperatures.
During a previous inspection, the IE inspector observed daily curing reports that indicated water tank (No. 7) temperatures averaged approximately 80 F.
A review of the test laboratory procedures did not contain corrective meacures to be initiated when curigg water temperatures were not within the ASTM C192 limits of 73.4 I 3 F.
During this inspection, the licensee provided record documents which reflect no safety-related test specimens were being cured in tank No. 7 during the higher water temperatures.
In addition, the Peabody Testing Procedure has been revised and now contains the corrective action to be initiated in the event out-of-specification temperatures are encounted. This matter is considered resolved.
3.
Site Tour
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The IE inspectors walked through the Reactor Building cnd Auxiliary Building to inspect the status of construction and housekeeping.
No items of noncompliance or deviations were identified.
4.
ASME Certification Review During this inspection, the IE inspector conducted a document review relative to the current status of the ASME Certificates of Authorizations issued to the principle contractors at the Waterford, Unit 3 facility.
The contractors and their specific authorizations are as follows:
Site Survey Company Activity Authorization Expires Conducted Ebas co A/E N, NA & NPT 6/14/82 May 1979 Tompkins-Beckwith, Field Piping NA & NPT 1/19/82 November 1978 Inc.
Installation
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Site Survey Company Activity Authorization Expires Conducted Nuclear Instal-NSSS Piping NA & NPT 7/14/81 August 1979 lation Services Installation Co.
Ikrcury Co.
Field Piping /
NA & NPT 4/7/81 August 1979 Instr. Instal-lation Gulf Engineering Equip. Handling NA & NPT Interim June 1979 Co., Inc.
& Setting letter 9 / 30/ 79 No items of noncompliance or deviations were identified.
5.
Reactor Building Dome An inspection was conducted of construction activities performed by Fegles-Power Service Corporation under Contract No. W3-NY-3, " Concrete thsonry Construction of Reactor Shield Wall and Dome."
During this inspection, the licensee notified the on-site IE inspector
~ a construction deficiency within the context of 10 CFR 50.55(e)(iii). Areas of inadequate consoli-dation were identified upon removal of the forms from concrete placements No. 521-1A and 521-1B. These placements constitute the north and south quadrants of the transition parapet from shield wall to dome. Placement No. 521-1A occurred between azimuth 3300 and 60 while placement No. 521-1B was between azimuth 150 and 240. Both placements had a height from elevation 179 to 190.5 feet.
The licensee Quality Assurance (QA) engineer, present during the placement, identified a nonconformance with Fegles Procedure No. CP 303-3, Revision 2,
" Concrete Placement and Inspection." The QA engineer found that the con-crete was not being adequately vibrated, immediately after placement, in the forms during the early stages of the placement.
The Site Surveillance Report generated by the licensee QA engineer was reviewed by the IE inspector.
In addition, the Fegles QC Inspection Discrepancy Lists and the Concrete Placement Inspection Checklists were also reviewed.
These documents identify inadequate consolidation of concrete to have occurred during the placements.
The Ebasco Nonconformance Report (NCR), generated as a result of the non-conforming concrete (Report No. W3-1576),was also reviewed by the IE inspector. As part of the Engineering Disposition of the NCR, 4 inch diameter cores were required in a preliminary effort to identify the extent of the nonconforming concrete. The firnt set of core samples taken from the concrete placement was inspected by the IE inspector.
No areas of inadequate consolidation could be identified in the cores observed. Sub-sequent coring, to include the placement interfaces, has been planned by the licensee in an effort to accurately identify the extent of the honeycomb-4-1209 352
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areas.
These efforts shall be reviewed during subsequent IE inspections in order to determine that the core samplings taken adequately describe the extent of the honeycomb areas.
The licensee has also planned to perform nonic testing of the concrete.
The results of the licensee's testing program shall be reviewed during the performance of the sonic testing.
No items of noncompliance or deviations were identified.
6.
Exit Interview The IE inspectors met with licensee representatives (denotod in paragraph 1) at the conclusion of the inspection on August 24, 1979 The IE inspectors summarized the scope and findings of the inspection.
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