IR 05000443/1979001
| ML19308A299 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/06/1979 |
| From: | Bateman W, Folsom S, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19308A298 | List: |
| References | |
| 50-443-79-01, 50-443-79-1, 50-444-79-01, 50-444-79-1, NUDOCS 7903200333 | |
| Download: ML19308A299 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-443/79-01 Report No.
50-444/79-01 50-443 Docket No.
50-444 CPPR-135 A
License No. e ppp _1 x Priority
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Category a
Licensee:
Public Service Company of New Hampshire 1000 Elm Street
_ Manchester, New Hampshire 03105 Facility Name:
Seabrook Station, Units 1 and 2 Inspection at: Seabrook, New Hampshire Inspection conducted: January 15-18, 1979 Inspectors:
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S. A. Folsom, Reactor Inspector ddte' signed C.44 6%-
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"date/ signed W. H. Bateman,_Feactor Inspector G C W /w 2/i n R. A. McBrearty, eactor I/isdector date signed r
Approved by: [///2thev h hr-[/7/f RC&ES Branch { Chief, Projects Section, date' signed R. W. McGauq)(
Inspection Summary:
Inspection on January 15-18,1979 (Combined Reoort Nos. 50-443/79-01; 50-444/79-01)
reas Inspected: Routine, unannounced inspection by tnree regional based inspectors of construction activities.
The inspection included a review of previously identified unresolved items, observation of work in progress in the construction area, review of reactor pressure vessel unloading and handling procedures, and examination of concrete placement records.
The inspectors performed a construction site tour. The inspection involved 78 inspector-hours onsite by three regional based inspectors.
Results: No items of noncompliance were identified.
7903200333 Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted Yankee Atomic Electric Company Mr. F. W. Bean, Quality Assurance Engineer, Electrical Ms. J. Buehler, Educational Center Representative
- Mr. D. L. Covill, Quality Assurance Engineer, Civil Mr. W. J. Gagnon, Quality Assurance Engineer, Mechanical Mir. J. H. Herrin, Site Manager Mr. P. A. Nason, Staff Engineer Mr. R. P. Pizzuti, Construction Manager
- Mr. J. W. Singleton, Field Quality Assurance Manager Mr. A. J. Stewart, Site Geologist Mr. T. M. Sherry, Director, Constructior. (Westborough)
Mr. G. Thomas, Startup Engineer Pittsburgh-Des Moines Mr. J. Hill, Site Construction Superintendent Morrison-Knudsen Company Mr. J. N. Allan, Project Manager United Engineers and Constructors Mr. P. Francis, Supervisor, Mechanical Operations Mr. R. Hawley, Area Superintendent
- Mr. R. N. Moyer, Field Superintendent, Quality Assurance / Quality Control Mr. J. B. Zabielski, Concrete Superintendent Pittsburgh Testing Laboratories Mr. W. S. McKay, Manager, Quality Assurance (Pittsburgh)
Mr. H. Ruffner, Site Manager, Test Laboratory Supervisor Royal Globe Insurance Companies
- Mr. C. O'Sullivan, Authorized Nuclear Inspector
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Perini Power Constructors Mr. P. Antonich, Assistant Superintendent Quality Assurance Mr. R. Capra, Project Superintendent Mr. C. E. Schreiber, Quality Assurance Inspector
- denotes those present at the exit interview.
2.
Plant Tour The inspector performed a walk-through inspection of the construction site and observed completed tork and work in progress in addition to activities in the storage areas.
Particular note was taken of the presence of quality control inspectors and evidence of quality control such as inspection records, material identification, nonconforming material identification, and periodic maintenance data on materials and equipment in storage.
Craftsmen, inspectors, supervisory personnel and engineers were interviewed.
Specific activities examined included installation of rebar and embeds in containment walls and reactor pit, installing formwork on inside face of equipment vault, dewatering containment slab crea, shotblasting containment knuckle plates in preparation for painting, and concrete compressive strength testing.
No items of noncompliance were identified.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved items (443/78-06-03 ; 444/78-06-03): Failure to control batch plant effluent.
The inspector, accompanied by the licensee's staff environmental engineer, examined the drainage system in the batch plant area, and traced the drainage path from selected areas to the permanent settling basin.
The effluent control appeared to be consistent with the licensee's commitments.
4.
Reactor Vessel Installation Activities The Unit I reactor pressure vessel and closure head will be delivered by seagoing barge to an off-loading area, and then, via an overland route, to the onsite storage area.
The barge will be grounded prior to off-loading the reactor pressure vessel and closure head.
Timbers will be used to equalize the barge deck / landing ramp grade level. When the appropriate preparations have
been completed the reactor vessel will be set aboard a 420-ton rated capacity,12 axle, hydraulic semi-trailer.
The vessel closure head will be set aboard a 125-ton capacity low bed semi-trailer. The components then will be transported over public roads to the site where they will be placed in outside storage.
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The inspectors examined the barge off-loading area and the overland route which will be followed by the reactor vessel and closure head.
Two bridges along the route will be reinforced to support the re-quired load. The licensee stated that all necessary permits and approvals have been granted for this work.
No itens of nonccmpliance were identified.
5.
Procedure Review The inspector reviewed selected documents and drawings associated with the reactor vessel off-loading, handling and storage activities, and interviewed licensee representatives in order to ascertain the adequacy of the procedures and to assure that the activities are properly controlled.
The following were included in the inspector's review:
Frank W. Hake, Inc. Documents:
Quality Assurance Manual For Shipping, Storing and Handling of
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Items For Nuclear Power Plants Procedure No. QAP-4, Revision 3,9/27/78, Training and Qualifi-
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cation of Personnel Procedure No. QAP-5, Revision 2,9/23/76, Instructions, Pro-
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cedures and Drawings Procedure No. QAP-8, Revision 4, 12/4/78, Inspection
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Procedure No. QAP-9, Revision 4, 9/27/78, Test Control
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Appendix 1, Revision 4,9/27/78, Equipment Handling Record
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Procedure for off-loading and moving the reactor vessel," Jacking, Hauling and Handling of the Unit Nos.1 and 2 Reactor Pressure Vessel, Reactor Head, Reactor Pressure Vessel "0" Ring Box and Unit Nos.1 and 2 Diesel Generator Fuel Oil Storage Tanks? 12/12/78
Drawing No. 538 BR-1, Revision 4,9/25/78, Yemporary Rein-
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forcing Blackwater River Bridge (NH 215/056) Route 286, Seabrook, N.H.
Drawing No. 539 BM-1, Revision 4,3/23/78, Temporary Rein-
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forcing Bridge 136/051 on N.H. 286 at Seabrook, N.H. Over Boston and Maine R.R.
United Engineers & Constructors Inc. Documents:
Field Quality Assurance Manual for Seabrook Station Public
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Service Company of New Hampshire Quality Control Procedure QCP-7-2, Revision 0,9/10/76,
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Receiving Inspection of Westinghouse NSSS Items For Seabrook Station Quality Control Procedure QCP-13, Revision 6, 7/28/78, Handling
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and Storage Control For Seabrook Station Quality Control Procedure QCP-17-1, Revision 2,1/23/78, Records
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Review Quality Control Procedure QCP-17-2, Revision 2,2/17/78, Quality
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Assurance Records In addition, the inspector reviewed the following sections of Westinghouse Electric Corporation NSSS Component Receiving and Storage Criteria, Volume 1 - Mechanical Equipment:
Reactor Vessel Shop Order 105
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Attachment 105C - Reactor Vessel Receipt, Hu iling and Storage
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for Combustion Engineering Co. Vessels The inspector found that adequate provisions have been made for barge off-loading and transporting the reactor vessel and closure head. The onsite storage preparations appear to meet the Westinghouse stcrage recommendations for the components.
No items of noncompliance were identified.
6.
Containment Concrete Placement Records The inspector examined work in progress on a 145-cubic yard concrete placement in Unit I reactor pit slab No.1-CI-1, elevation - 53 ft.,
placed on January 16, 1979.
Placement operations observed included concrete purping, consolidation, and finishing; also, the presence of quality control personnel at the batch plant and at the placement location, engaged in testing concrete for density, air content, temperature, and slump.
The records relating to this placement were examined on January 17, 1979.
Documentation reviewed included:
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Perini Concrete Lift Document Review Checklist, January 16, 1979, which indicated completion of placement documentation including Concrete Placement Plan, truck records, pre-placement, placement, and post-placement records.
Perini Concrete Placing Scheme, January 15, 1979.
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Perini Preplacement Inspection Report (which referenced Quality
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Assurance Procedure 10.5, Revision 2, and Drawings F-101412 and 016-RI-Wl). This report included information regarding surveys, placement preparation, weather protection, reinforcing steel, formwork, and embedments.
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Perini Concrete Placement Report, Revision 1, January 16, 1979.
This report included information on checkout card completion, placement details, vibrators used, concrete sampled, form integrity maintained, and problems encountered. This report was signed by the Level II QA Placing Inspector and by the Chief Inspector.
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Perini Concrete Placement Checkout Card, January 16,1979, which recorded that, for examples, the concrete was categorized as moderate massive, maximum temperature 800F, safety-related, slump 2-4 inches, Mix Code Nos. 4-AWR-1 1/2 (.48) and 4 PAW l 1/2 (.48) Marquette Type II.
This report had been signed by construction supervision including piping, electrical, formwork, reinforcing steel, and concrete placement.
The report was also signed by the constructor's (UE&C) Resident Engineer on January 12, 1979.
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Pittsburgh Testing Laboratory Concrete Strength Test Report, which referenced ASTM 39-74, and listed 28 test cylinders to be tested for required compressive strength (4000 lbs design) at 7, 28 and 90 day Pittsburgh Testing Laboratory Concrete Load Batch Tickets, Nos.
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017928 through 017963, Ja nua ry 16, 1979, which included data on lift location, truck revolutions, ambient temperature, test cylinder numbers, and quantities of cement, water, admixtures, and aggregate.
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Perini Concrete Postplacement Inspection Report, January 16, 1979.
This report referenced Drawing Nos. F-101412 and 016-R-Wl, and Concrete Specification 13-3, Revision 4.
The report was not complete at the time of the inspection as curing was still in process.
No items of noncompliance were identified.
7.
Exit Interview The inspector met with the licensee and contractor representatives (indicated in paragraph 1) at the conclusion of the inspection on January 18, 1979.
The inspector summarized the scope and findings of the inspe-tion.
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