IR 05000443/1982014
| ML20028D622 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 12/04/1982 |
| From: | Durr J, Varela A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028D610 | List: |
| References | |
| 50-443-82-14, 50-444-82-12, NUDOCS 8301190328 | |
| Download: ML20028D622 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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REGION I
Report No.
50-443/82-14 50-444/82-12 Docket No.
50-443 50-444 License No. CPPR-135 CPPR-136 Priority
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Category A
Licensee:
Public Service Company of New Hampshire
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100 Elm Street Manchester, New Hampshire 03105 Facility Name:
Seabrook Station, Units 1 and 2 Inspection At:
Seabrook, New Hampshire Inspection Conducted: November 2-5, 1982 (.
N NC. 2, Ii82 Inspectors:
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A.A.Vadela,ReactorEngineeringInspector date Approved by:_
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P.~Durr, Chief, Materials and Processes I dite Section
Inspection Summary:
Unit 1 Inspection on November 2-5, 1982 (Report No.
50-443/82-14)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector l
of quality records and work obser"ation of the refueling water storage tank and
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the structural support installation and erection for the reator coolant pumps.
The inspector also performed a plant inspection tour.
The inspection involved 20 inspector-hours on-site.
Results: No violations were identified.
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Inspection Summary:
Unit 2 Inspection on November 2-5, 1982 (Report No.
50-444/82-12)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of quality records and work observation of concrete activities for the primary shield wall and reactor supports embedded in the wall.
The inspector also performed a plant inspection tour. The inspection involved 10 inspector-hours on-site.
Results: No violations were identified.
8301190328 830106
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PDR ADOCK 05000443
pDR
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CETAILS 1.
Persons Contacted Yankee Atomic Electric Company (YAEC)
- F. W. Bean, Field QA Engineer
- D.
L. Covill, Lead Civil Q.A. Engineer
- R.
E. Guillette, Field Q.A. Engineer
- R. C. Julian, Field Q.A. Engineer
- W. T. Middleton, Field Q.A. Engineer
- B. J. Mizzau, Field Q.A. Engineer
- J. Philbrick, Senior Project Engineer (Framingham)
- J. W. Singleton, Field Q. A. Manager
- R. K. Tucker, Lead Mechanical Engineer (Framingham)
- S. Sadosky, Field Q.A. Engineer United Engineers and Constructors (UE&C)
- J. A. Grusetskie, Assistant Manager Site Engineering
- D. C. Lambert, Field Supervisor - Q. A. Engineer P. Sullivan, Concrete Superintendent Perini Power Constructors (PPC)
G. Myers, Lead Field Q.A. Engineer - Concrete R. Narva, Supervising QA Engineer - Concrete S. Swijeski, Containment #2 Superintendent Pullman - Higgins (P-H)
J. Godfrey, Lead Mechanical Inspector S. Whitt, Mechanical Supervisor Pittsburgh - DesMoines Steel Co. (PDM)
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W. A. Steiger, Q.A. Manager USNRC
- A. C. Cerne, Senior Resident Inspector
- Indicates attendees at exit interview November 5, 1982.
The inspector conferred with other licensee, construction manager and contractor personnel during the course of the inspectio.
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Plant Inspection - Tour (Units 1 and 2)
.The inspector' observed work activities in progress, completed work and plant status in several areas of the plants during a general inspection of construction activities.
The inspector examined work for any obvious defects, noncompliance with regulatorf requirements or license condi-tions.
Inspection personnel were observed performing required inspections and those interviewed were knowledgeable in their work activities.
Craft persc.nnel, supervision and construction engineers were interviewed as such personnel were available in the work areas. Areas inspected included:
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i Unit 1:
Seal welding of reactor vessel refuel annulus, concrete preparation for enclosure building wall, 'nstallation of heat exchanger in fuel storage building, condensate storage tank
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erection and preparation for its concrete enclosure, erection of reactor coolant pump vertical columns and construction of the refuel water storage tank.
Unit 2:
Containment building steel liner completion to spring line and installation of temporary aluminum dome and, interior of con-tainment concrete activities for the primary shield wall, cubicle walls and equipment supports up to elevation - 10.
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No violations were identified.
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3.
Unit 1 - Reactor Coolant Pump (RCP) Vertical Columns - Record Review _
l Quality records of work activities performed by Pullman-Higgins (P-H) in receipt inspection and installation / erection of the vertical columns for
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each of four reactor coolant pumr; were reviewed. The reactor coolant pump column assembly consists of the following major components: : column base; column subassembly and column bearing pin. Three individual columns provide support for each pump.
Lateral support for seismic and blowdown
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loading is provided by three lateral tie bars.
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l The primary purpose of this inspection was to determine whether the
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documentation requirements were met. The following criteria formed the basis for the inspector's review of the quality records generated and maintained by P-H:
i Document F-815199 Major NSSS Equipment Setting
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Document FP-50509 Steam Generator and Reactor Coolant Pumps Vertical l
Columns-Document FP-52511 Erection of RC System Equipment, Support Structures and Components i
Document No. FI-124 Reactor Coolant Pump Column Assembly
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Document FI-102 Bolt Tightening for NSSS Support Structures, ASME
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Section III Winter of 1977 Addenda P-H Field Instruction for Installing RCP Vertical Columns and P-H QA
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l Procedures.
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The material receipt records for the unit #1 RCP Supports, column bases and the lateral supports provide test certificates and confirmatory reports on code requirements. A sample review of pump "D" column installation was made in the following quality records:
Instruction / Checklist Package prepared for Handling, Installation ar.d
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Testing These records contain sign-off by the P-H inspector, the Westinghouse technical representative, and the authorized nuclear inspector at the prescribed hold points.
They include classroom training records, pre-handling and handling instruction checklists, and approval of ECA
- 08-1557-C by UE&C and Westinghouse.
The inspector observed the records to be complete. Additionally the inspector visited the containment to observe the vertical columns and lateral supports for each pump. The pump internals have not been installed, however, the columns, base bolting, and pin connection to the pump housing are complete. The inspector also reviewed a licensee surveillance report of the above installation / erection.
It was conducted in accordance with YAEC Master Check List #1A-39 and resulted in no outstanding items.
The inspector determined by independent evaluation of the foregoing records that the RCP columns and lateral support were constructed and installed in accordance with NRC requirements and SAR commitments.
No violation were identified.
4.
Unit 1 - Refuel Water Storage Tank Quality records of work activities performed by Pittsburgh Des Moines (PDM) in receipt inspection and construction welding of the 475,000 gallon stainless steel refuel water storage tank were reviewed.
Governed by UE&C's Specification #9763-006-246-1 Rev. 5 and QA/AC Requirements
- 9763-WS-1 the design for the tank, its materials, nozzles, piping, connec-tions and welding must conform to ASME Section III, Subsection NC and Regulatory Guide 1.48.
The tank is seismic Category I.
The inspector determined by record review, by direct observation and independent evalua-tion of work performance of the completed work, that the safety related structure outside the containment was constructed in accordance with NRC requirements and SAR commitments. These requirements were implemented and explicitly identified by PDM on their drawings #14084-WS-15 revision on 12-2-81 and, construction drawing series E-1 through E-8, HS #1-4 and WL
- 1-5.
The following PDM QC records were reviewed, discussed with responsible personnel and independently evaluated for conformance to criteria identified in the above requirements:
Fabrication checklist and sign-off to release the material shipments
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received at the site from PDM's Neville Island, Pittsburgn Fabrication shop including ASME III Division I " Certificate of Authorization" transfer to Seabrook
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Fabrication checklist and QA release for field construction
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Construction foreman and QA sign-off:
fit-up and tack, visual
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inspection of seam welds, dye penetrant tests, vacuum box tests, hold point for ANI and,100% radiography testing of all welds Weld material and welder qualifications
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Additionally, the inspector reviewed the following QA audit reports for conformance to 10 CFR 50, Appendix B.
PDM corporate audit #82-514.
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PSNH/YAEC audit number SA 462 CS 135, SA 629 CS 220, and SA 645 CS
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230 dated January 20, 1982 through September 14, 1982 and pertaining
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to PDM.
YAEC Field QA Group Surveillance Report covering 100% of PDM
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radiography:
processed film, check of densities, film artifacts, identification and completeness of documentation.
The above QA audits were complete and closed where deficiencies were
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revealed.
No significant deficiency was identified.
Corrective action for identified deficient items were resolved and accepted by the respec-
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tive audit manager.
No violations were identified.
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5.
Unit 2 - Containment Interior Concrete Activities Pertinent work and quality records associated with preparatory concrete activities, pumpline conveyance and placement of 255 cubic yards of.4,000 psi concrete (made 9/17/82) for the first pour #2 CI-12 of the primary shield wall were reviewed.
Perini Power Constructors' (PPC) procedures and documentation of the placement between elevation (-)26' and (-)16'-6" were reviewed to verify compliance with SAR commitments and referenced I
codes and standards.
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Documentary evidence was reviewed to ascertain whether the l
records are in conformance with the above procedures and whether the
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records reflect work accomplishment consistent with applicable require-
ments in the following areas:
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Preplacement prepara.tfon and sign-off by craft supervision; engineer
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chech uk, 10 inspection reports on preparation, concrete placing scheme / equipment, manpower and contingency preparedness; "satisfac-
tory" QC preplacement inspection report and UE&C release for concrete
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placement.
No violations were identified.
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Work Observation Completed elements of concrete preparations for the second pour #2 CI-16 of the primary shield wall between elevation (-)16'-6" and (-)11'-11" were ob-served and discussed with responsible field engineers and construction :soper-visers.
Particular note was taken of bolt anchors located in this placement for the reactor vessel vertical and horizontal ring girder supports.. Location of these bolts have been verified by a template made from the "As-Built" reactor vertical support and the reactor support ring girder.
Surveyors, field engineers and QC personnel were observed during the preplacement check and those interviewed were knowl-edgeable of their activities.
No violations were identified in the work observed.
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Exit Interview The inspector met with licensee's representatives (denoted in Paragraph 1) at the conclusion of the inspection on-November 5, 1982, at the con-struction site. The inspector summarized the findings of the inspection.
The licensee acknowledged the inspector's comments.
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