IR 05000443/1978016
| ML19281A644 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 01/12/1979 |
| From: | Fasano A, Folsom S, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19281A638 | List: |
| References | |
| 50-443-78-16, 50-444-78-16, NUDOCS 7903260140 | |
| Download: ML19281A644 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-443/78-16 Report No.
50-444/78-16 50-443 Docket No.
50-444 CPPR-135 A
License No.
CPPR-136 Priority Category A
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Licensee:
Public Service Company of New Hampshire 1000 Elm Street Manchester, Massachusetts 03105 Facility Name:
Seabrook Station, Units l' and 2 Inspection at:
Seabrook, New Hampshire Inspection conducted:
December 12-15, 1978 ff !79 Inspectors:
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Seth A. Folso eactor In pector
/ da'te signed F^Waa ik /n A. N. Fasano, R,eactor I6spector
/ date signed date signed Approved by:
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h;;g(;.,)9)[ R. W. McGaughd @f, Projects Section, f date/ signed , RC&ES Branch (/ Inspection Summary: Inspection on December 12-15,1978 (Combined Report Nos. 50-443/78-16; 50-444/78-16) Areas Inspected: Routine, unannounced inspection by two regional based inspectors of construction activities. The inspection included a review of previously identified unresolved items; observations of work in progress in the construction area and at the material storage area;'and a review of implementing procedures for safety-related structures and supports. The inspectors performed a construction site tour. The inspection involved 56 inspector-hours onsite by two NRC regional based inspectors.
Results: Of the 3 areas inspected, no items of noncompliance were identified in 2 areas; one item of noncompliance was identified in one area (Infraction - failure to control material storage - Paragraph 4).
790326014o Region I Form 12 (Rev. April 77)
. .. DETAILS ' 1.
Persons Contacted Yankee Atomic Electric Company Mr. F. W. Bean, Quality Assurance Engineer, Electrical Mr. B. B. Beckley, Manager, Nuclear Projects (Manchester)
- Mr. D. L. Covill, Quality Assurance Field Engineer, Civil Mr. W. J. Gagnon, Quality Assurance Engineer, Mechanical
- Mr. J. H. Herrin, Site Manager Mr. G. F. Mcdonald, Jr., Senior Quality Assurance Engineer (Westborough)
Mr. W. J. Miller, Manager, Quality Assurance (Westborough) Mr. P. A. Nason, Staff Engineer Mr. J. F. Nay, Jr., Quality Assurance Engineer, Mechanical Mr. R. P. Pizzuti, Construction Manager
- Mr. J. W. Singleton, Field Quality Assurance Manager Mr. T. M. Sherry, Director, Construction (Westborough)
Pullman /Hiqqins Mr. R. G. Davis, Field Quality Assurance Manager Pittsburgh Des Moines Mr. W. Stiger, Site Quality Assurance Superintendent United Engineers and Constructors (UE&C)
- Mr. R. N. Moyer, Fieid Superintendent, Quality Assurance / Quality Control
- Mr. N. A. Vitale, Supervisor, A&R Royal Globe Insurance Companies
- Mr. C. O'Sullivan, Authorized Nuclear Inspector Perini Power Constructors (PPC)
- Mr. P. E. Bruce, Superintendent, Quality Assurance
- Mr. W. A. Dileo, Project Manager
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denotes those present at the exit interview
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2.
Plant Tour The inspector performed a walk-through inspection of the construc-tion site and observed completed work, and work in progress, in addition to storage and laydown 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 equipment calibration tags. Craftsmen, inspectors and supervisory personnel were inter-viewed.
Specific activities examined included setting support angles in Unit 1 reactor building mat, installation of rebar and wall embeds in Unit 1 equipment vault, backfill compaction and setting forms for slab at Form "S" column line.
No items of noncompliance were identified.
3.
Licensee Action on Previous Inspection Findings (Closed) Noncompliances (443/77-09-01; 444/77-07-01; 443/78-06-01; and,444/78-06-01): Unmonitored turbid effluents discharged to wetlands adjacent to the plant. The inspector determined that the use of temporary settling basins had been discontinued in May 1978.
All site runoff water is now diverted by pipelines and ditches to the permanent settling basin which is regularly monitored for turbidity.
The inspector toured the site with the licensee's staff environmental engineer and traced the drainage path from several selected locations to the permanent settling basin. The effluent control appeared to be consistent with the licensee's commitments.
(Closed) Noncompliances (443/78-06-02; 444/78-06-02): Failure to maintain drainage patterns in hemlock ravine vegetation.
The inspector determined that the construction work in the hemlock ravine area had been completed in May 1978, and that no subsequent construction work had been performed in the general area of the hemlock ravine. Accompanied by the licensee's staff environmental engineer, the inspector examined the hemlock ravine and confirmed that no adverse conditions existed in this or adjacent areas.
4.
Safety-Related Structures and Support - Quality Assurance Implementing Procedures The inspector interviewed cognizant licensee personnel, reviewed documentation and visually inspected storage and work areas. Work procedures, specifications and QA program documentation were examined for (1) conformance to committed QA program requirements; (2)
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inspection point designation; (3) receiving inspection require-ments, with attributes to assure that components are checked for damage, identification, storage classification, and, report require-ments; (4) attributes addressing surveillance activities related to storage, protection, issue and identification of structures; (5) inspection and installation procedures which addressed the type, size and location of components such as clips, bolt holes, anchors and mounting pads; and (6) procedures assuring the nondestructive examinations, and installation records..The inspector reviewed the following material for program content, with particular attention to tha above listed attributes: Engineering and Contract Statements of Work, Job Order 9763 -- (UE&C): Package No. 9 - General Concrete Construction, Steel Erection and Circulating Water Pipe Installation, 6/30/77; Pkg. No. 18, Structural Steel Work, 1/28/77 -- UE&C Specification 9763-12-2 Structural Steel Erection, 5/23/75 UE&C Specification 9763.006-12-5 Fabrication of Safety-Related -- Structural Steel Work, 9/6/75 UE&C handard Documents Related to Specifications: WS-3, -- Requirements for Welding and Nondestructive Examination of Structural Steel, Revision 1; QAS-1, Quality Assurance Admini-strative and System Requirements for Nuclear Safety Class Items, Revision 6; Special Conditions 9763-4224 for Purchases of Material and Equipment, 2/1/78; Instructions for Site Management System 9763-RM-1, 5/26/78; Material and Processing Requirements for Bending of Welded Studs, Reinforcing Bars and Anchor Bolts 9763-MPS-3, 8/16/78 -- UE&C Field QA Manual for Seabrook Station: QCP-7-1, Receiving Inspection of UE&C Purchased Items, R3; QCP-8, Material Control, R3; QCP-10-1 Site Surveillance, Rl; QCP-13, Handling and Storage Control, R6; QCP-17-1, Record Review, R2; QCP-17-2, QA Records, R2 UE&C Field General Construction Procedures, FGCP: 3, Receiving, -- Inspection and Storage of Nuclear and Safety-Related Equipment and Material, (R)S; 8, General Housekeeping During Construction of Nuclear Plants, Rl; 9, Preventive Maintenance and Protection of Nuclear or Safety-Related Equipment, R3; 10, Maintenance, Inspection, Testing and Operations of Construction Lifting Equipment, Rl; 15, Design Change Notices, Field Change Requests, and Engineering Change Approvals, R4; 16, Handling of Nuclear and Safety-Related Material and Equipment, R.- ,
Perini Procedures: AP 4.0, Perini Purchasing, Rl; AP 5.0, -- Preparation, Review and Approval of Project Procedures, Rl; QAP-1, Organization, R0; QAP 1-1, Initiation of Stop Work Action, R0; QAP 2.0, Qualification and Certification of QA Personnel, R0; QAP 6.0, Control of Documents, R2; QAP 7.0, Supolier Qualification and Surveillance, Rl; QAP 8.0, Identi-fication and Status Control, R1; QAP 10.8, Structural Steel Inspection, R0; QAP 12.0, Calibration Control of Equipment, R2; QAP 13.1, Receiving and Storage Inspection of Material and Equipment, Rl; QAP 15.0, Reporting of Nonco.nformances, Rl; QAP 16.0, Corrective Action, R0; QAP 17, Records and Filing, Rl; QAP 18.0, Surveillance and Audit of Safety-Related Activities, R1 Perini Field Civil Construction Procedures: FCCP 152, Handling -- and Storage of Structural Steel and Miscellaneous Metal Prior to Erection, R0; FCCP 153, Erection of Structural Steel and Mis-cellaneous Steel, R0; FCCP 154, Installation and Tightening of High Strength Bolts Using the Load Indication Method, R0; FCCP 156, General Weld Procedure for Structural Steel, R0 Perini Field General Construction Procedures: FGCP-2, Drawing, -- Specification and Document Control, R2; FGCP-3, Receiving, In-spection and Storage of Nuclear and Safety-Related Equipment and Material, R0; FGCP-10, Maintenanca, Inspection, Testing and Operation of Construction Equipment, R0; FGCP 110, Handling of Safety-Related Material, R0 UE&C Specification 9763.006-12-1 defines Owner as Public Service Company of New Hampshire; Engineer Supervisor as Yankee Atomic Electric Company; Engineering Construction Manager as UE&C.
The Contractor for the structural steel on site is Perini Power Constructor, Inc. The QA/QC functions are established so that first level QA/QC is per-formed by the Constructor with second level being performed by UE&C.
A third level audit function is performed by the Engineering Super-visor, YAEC.
The specification lists the following structures where safety re-lated structural steel will be used: Service Water Pump House - Structural Steel - - Prim y Auxiliary Building and RHR Vault Area - Ccmat.went and Diesel Generator Building Fuel Storage Building - - Waste Processing Building - Emergency Feedwater and Pump Building - Main Steam and Feedwater Pipe Chase (East & West) - Mechanical Penetration Area - Personnel Hatch Area
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Containment Enclosure - Ventilation Area - Service Water Cooling Tower, including Switch Gear Room - - Hydrogen Recombiner Structure Applicable Codes and Standards at the time of contract award shall apply. The principal Codes and Standards are: AISC; SSPC; ASTM; AWS-Dl.1; ANSI N5.12, 45.2,101.2 and 101.4.
Bolts are to be ASTM A325 and/or 490.
The bolts shall be bearing type. The connection shall be designed taking into account the location of thread with respect to shear planes.
Thread design parameters shall be indicated on steel detail drawings.
The inspector visually inspected the C level storage of the received A325 bolts. The inspector also examined the holding facilities for equipment handling accessories.
UE&C procedure FGCP-10, Maintenance, Inspection, Testing and Operation of Construction Lifting Equipment, Revision 1; Rigging Lift Authorization (Letter No. SBF-1137), and Riggirg Accessories (Letter No. SBF-ll37), were used as the basis to inspect rigging accessories.
It was noted by the inspector that some of the slings lacked unique identification tags.
Identification of slings and lifting accessories is needed to implement procedure FGCP-10 and to control the use of the accessories. The use of the referenced letters appears to change or modify procedure FGCP-10.
The inspector questioned the use of these letters which appear to change approved procedures and appear to lack complete distribution and review.
Inasmuch as no safety-related lifts had been perfonned to date, this item is unresolved pending the licensee's developp of fixed identification of lifting accessories, such as slings,30t a:Td evaluation of the procedure for,and the use and distribution of, letters affecting approved procedures. (443/78-16-01, 444/78-16-01).
The laydown area for the structural steel was inspected by the NRC inspector, accompanied by a licensee representative.
Section S40-D in particular and adjacent sections were examined on December 13, 1978.
It was noted by the inspectors that the dunnage in use varied in size and that structural steel members were in contact with the ground.
Specifically, one member under member 1A70LC5 touched the ground. Three other examples of contact were noted in the S40-D area.
In addition, one 5 gallon can in this area, con-taining angle clips, was full of frozen water.
Three similar cans were noted in an adjacent area under sirailar conditions.
Also, a loose " Acceptance Tag" was on the ground beside one of the can. .<
Failure to control the storage of safety-related material from deterioration is an item of noncompliance relating to Criterion XIII of Appendix B of 10 CFR 50.
This item is an infraction (443/78-16-02,444/78-16-02).
5.
Reactor Pressure Vessel Handling Procedures The Frank W. Hake Company, Inc., contractor for the offloading and movement of the reactor pressure vessel from the barge slip to the site laydown pads had submitted their Quality Assurance Manual and implementing procedures to the licensee for approval.
The inspector examined these documents briefly, and a detailed review will be performed during a subsequent inspection: The documents examined were: Hake Quality Assurance Manual for Shipping, Storage and Handling - of Items for Nuclear Power Plants, Revision 4, September 27, 1978 - Hake Procedure for Jacking, Hauling and Handling of the Unit Nos. 1 and 2 Reactor Pressure Vessel, Reactor Head "0" Ring Box and Units 1 and 2 Diesel Generator Fuel Oil Storage Tanks, October 23, 1978 - Hake Procedure for Jacking, Hauling and Handling Four-Loop Internals, November 15, 1978 No items of noncompliance were identified.
6.
Unresolved Items Unresolved items are matters about which r in#;c~ation is re-quired in order to ascertain whether thr.
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An un-q resolved item disclosed during this inspec'iri is d.. cussed in Paragraph 4.
7.
Exit Interview The inspector met with the licensee and contru: tor representatives (indicated in paragraph 1) at the conclusion of the i.spection on December 19, 1978. The inspector summarized cne scope and findings of the inspection. }}