IR 05000443/1979004
| ML19259C317 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 04/10/1979 |
| From: | Folsom J, Mcbrearty R, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19259C311 | List: |
| References | |
| 50-443-79-04, 50-443-79-4, 50-444-79-04, 50-444-79-4, NUDOCS 7906140582 | |
| Download: ML19259C317 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-443/79-04 Report No. En aaa/70 na 50-443 Docket No.60-444 CPPR-135 A
License No. cppn_1%
Priority
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Category A
Licensee:
public Service cnmnany of Now Hamnshire 1000 Elr Street Manchester. New Hamnshire 03105 Facility Name:
Seabrook Station Units 1 and 2 Inspection at:
Seabrook, New Hampshire
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Inspection conducted:
March 12 and 13, 1979 Inspectors:
[
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- [9[79 hSethA.Folsom,ReactorInspector date ' signed f66 7m fnaa G
+h/n RobertA.McBrearty,Re[ctorInspector dats signed date signed Approved by:
-Ir W )]i1hst lUfl9 R.W.McGaughy,Ihid,ProjectsSection, date sighed RC&ES Branch Inspection Summary:
Inspection on March 12 and 13, 1979 (Recort No. 50-443/79-04)
Areas Inspected:
Routine, unannounced inspection by two regional based inspectors of construction work in prngress, and licensee's action on previous inspection findings. The inspection involved 10 inspector-hours onsite by two NRC regional based inspectors.
Results: No items of noncompliance were identified.
Inspection on March 12 and 13, 1979 (Report No. 50-444/79-04)
Areas Inspected: Routine, unannounced inspection by two regional based inspectors of construction work in progress, reactor vessel handling and licensee's action on previous inspection findings. The inspection involved 10 inspector-hours onsite by two NRC regional based inspectors.
Results:
Nc items of noncompliance were identified.
2279 ;47 79061405&L Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted
_ Yankee Atomic Electric Company (YAEC)
Mr. F. X. Bellini, Geologist Mr. D. L. Corill, Quality Assurance Engineer, Civil Mr. W. J. Gagnon, Quality Assurance Engineer, Mechanical
- Mr. J. H. Herrin, Site Manager Mr. R. P. Pizzuti, Construction Manager (Westborough)
Mr. T. M. Sherry, Director of Construction (Westborough)
- Mr. J. W. Singleton, Field Quality Assurance Manager United Engineers and Constructors (UE&C)
- Mr. G. B. Frey, Project Superintendent Mr. R. Hawley, Area Superintendent
- Mr. R. N. Moyer, Field Superintendent Quality Assurance / Quality Control
- Mr. N. A. Vitale, Supervisor, Quality Assurance Royal Indemnity Comoany
- Mr. C. T. O'Sullivan, Authorized Nuclear Inspector F. W. Hake, Inc.
Mr. R. Chester, Truck Operator Mr. R. W. Ellis, Quality Assurance Manager Mr. F. W. Hake, Forerian Mr. L. Hanford, Tunne: C a rintendent Mr. K. Hansen, Superintendent
- danotes those present at the exit interview.
The inspector also interviewed other licensee and contractor per-sonnel during the inspection, including construction craftsmen.
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2.
Plant Tour A tour of the site was performed to observe the status of the project and construction work in progress.
The inspector noted the presence of Quality Control personnel inspecting work in progress.
Areas observed included:
Containments 1 and 2, Reactor Cavity Pits and Pipe Penetrations; Control Building, Storage and Laydown Areas.
Specific activities observed included piping alignment, rebar in-stallation, cadwelding, liver plate welding, concrete curing and finishing.
No items of noncompliance were iaentified.
3.
Correction - Inspection Reports 50-443/79-03 and 50-444/79-03 Investigation Summary Results, states in part:
"The concrete
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joint had been dried and heated prior to the subsequent con-cretement placement." This should be changed to read " Port-able propane torches had been ised to remove excess surface water remaining on the previously placed concrete."
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Section II, Page 5, Line 6 states in part:
...the use of
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portable propane torches to dry surface water remaining on the previously placed concrete...".
This should be changed to read, "...the use of portable propane torches to remove excess
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surface water remaining on the previously placed concrete...".
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Section IV, Line 7, states in part:
"It is common practice the heat the placement area, and to dry the previously placed concrete prior to the placements." This should be changed to read, "It is common practice to heat the placement area, and to remove excess surface water remaining on the previously placed concrete."
4.
Licensee Action on Previous Inspection Findinas (Closed)
Noncompliance (443/78-16-02 and 444/78-16-02):
Protec-tion of safety-related materials during storage.
The inspector examined the outdoor storage and laydown areas to ascertain con-fomance to UE&C Specification 9763.006-12-1, Structural Steel Work.
The structural steel was found to be stored properly.
The small parts, previously in baskets in outdoor storage are now stored indoors.
Increased surveillance of stored material was evidenced by'the storage surveillance documentation and by the condition of the stored materials.
No adverse conditions were found and thp inspector had no further questions in this area.
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5.
Reactor Vessel Installation - Observation of Work The Unit 2 reactor pressure vessel, closure head, and associated components were shipped by seagoing barge to the Hampton Harbor barge landing. They were then off-loaded and transported on a 12-axle carrier over 7 miles of highways and local roads to the onsite storage area. The test loading for this move was observed by the inspector as described in NRC Inspection Report 50-444/79-03.
The inspector examined the vessel and closure head at the laydown area prior to their removal from the carrier.
Protective fire-
. proof covers were intact, and no damage to the equipment was apparent.
The F. W. Hake Procedure, " Jacking, Hauling and Handling of the Seabrook Unit Nos. 1 and 2 Reactor Pressure Vessel, Reactor Head, Reactor Vessel 0-Ring Box and Diesel Generator Fuel Oil Storage Tanks," the governing directive for the work activities,was avail-able at the work area in the possession of the F. W. Hake Quality Assurance representative. The inspector observed the reactor vessel and closure head trailer off-loading operations and deter-mined that these activities were carried out in accordance with the procedural requirements.
An inspection of the reactor vessel and closure head revealed no exterior damage. All reactor vessel openings were covered and sealed against entry of contaminents and foreign material.
Pro-tective coatings on exterior surfaces appeared to be intact.
The licensee informed the inspector that, upon the arrival of the Westinghouse representative, a complete inspection would be performed which would include an examination of the reactor vessel interior, for damage and water intrusion.
No items of noncompliance were identified.
6.
Exit Interview The inspector met with the licensee and contractor representatives (indica ted in paragraph 1) at the conclusion of the inspection on March 13, 1979.
The inspector summarized the scope and findings of the inspection.
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