IR 05000354/1979002
| ML19269D305 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/19/1979 |
| From: | Fasano A, Mcgaughy R, Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19269D304 | List: |
| References | |
| 50-354-79-02, 50-354-79-2, 50-355-79-02, 50-355-79-2, NUDOCS 7906010039 | |
| Download: ML19269D305 (10) | |
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U.S. NUCLEA.' REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-354/79-02 Report No. 50-355/79-02 50-354 Docket No. 50-355 CPPR-120 License No.CPPR-121 Priority Category A
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Licensee:
Public Service Electric & Gas Company 80 Park Place Newark, New Jersey 07101 Facility Name:
Hope Creek Generating Station, Units 1 & 2 Inspection at:
Hancocks Bridge, New Jersey Inspection conduc
Februa-March 1, 1979 Gkf}frCf SfW/7f Inspectors:
aa
" LT arrow, Reactor Inspector date signed NaAk /W 3/ly/77
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A. N. Fasano, Reactor Inspector date' signed date igned Approved by:
[//h(u
/N < /8 /f7i R. W. McGaugt)ff, ef, Projects Section, date~ sfgned /
RC&ES Branch Inspection Summary:
Inspection on February 27-March 1,1979 (Combined Report Nos. 50-354/79-02; 50-355/79-02 Areas Inspected: Routine, unannounced inspection by regional based inspectors of the QC program for installation of pipe hangers and supports; and the subcontractors program for fabrication and installation of the containment liner.
The inspection involved 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> onsite by 2 NRC regional based inspectors.
Results: No items of noncompliance were identified.
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Region I Form 12 (Rev. April 77)
7906010037[
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DETAILS 1.
Persons Contacted Public Service Electric and Gas Company
- J. Dugan, Site QA Engineer
- P. J. Kudless, Principal Construction Engineer Bechtel Power Corporation (Bechtel)
B. Baim, Lead Field Welding Engineer J. Bloom, Engineering Survey Supervisor A. J. Bryon, Assistant Project Construction QC Engineer
- R. L. Hanks, Project QC Engineer
- W. F. Hindle, Project Field Engineer F. Kenitzer, Engineering Survey Supervisor S. Vezendy, Lead Welding QC Engineer Pittsburgh-Des Moines Steel Company (P-DM)
J. Benedetti, QC Engineer F. Hatmaker, Subcontractor Surveillance M. Steiger, QA Manager Schneider, Inc. (Schneider)
W. Goebel, Site QA Manager The inspector also talked with several other employees of the architect-engineer constructor.
- denotes those present at the exit interview.
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2.
Plant Tour A tour of the site was made to observe the status of the work and construction activities in progress.
The inspector noted the presence of and interviewed QC personnel inspecting work in prog-ress and construction personnel.
Areas observed included: in-stallation of containment drywell and suppression chamber; RHR and Core Spray pump wells; RCIC pump, HPCI pump and RHR piping.
No items of noncompliance were identified.
3.
Primary Containment Receipt and Storage The inspector reviewed P-DM's Field Receiving Reports FRR-1 and FRR-6 for receipt of Unit 1 drywell first course plates.
Receiv-ing inspection had been performed and FRR's signed in accordance with P-DM " Quality Assurance Manual for Nuclear Power Plant Com-ponents," Revision 2 and Specification C-152(Q), Revision 9
" Design Specifications for Furnishing, Detailing, Fabrication, Delivery and Erection of Primary Containment."
The inspector also observed storage of materials and subassemblies for Unit 1 and 2.
The inspector noted the presence of water which had collected on certain of the plates which were stored in the horizontal position.
Paragraph 18.2.2 of Specification C-152(Q)
requires that plates stored in this fashion shall be inspected at least every ten days and any collected water removed.
This problem had been identified by Bechtel.
The inspector reviewed the follow-ing documents:
Quality Action Request (QAR) No. F-050 dated September 15, 1978
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which identified the problem and requested corrective action.
Bechtel Letter BLC-238 to P-DM dated September 26, 1978 re-
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questing corrective action.
Bechtel 10M dated November 23, 1978 from contracts to QA
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stating the P-DM had taken exception to this section of the specification and that Bechtel Engineering was investigating the need for this requirement.
This item is unresolved pendin review by an NRC inspector of the resolution of this question.
354/355/79-02-01)
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4.
Pipe Support Installation - Unit 1 The NRC inspector visually examed the inprocess work on two support structures for conformance to weld requirements, general location, material used and pipe support clearances.
Final licensee inspec-tion on these two supports remains to be completed. The following identifies the supports inspected:
Drawing (Revision)
System Hydro-Load-Pounds 1-P-BC-019-H13 RHR 3386 1-P-BC-044-H04 RHR 4798 Support Hl3 was found to lack the 1/16" clearance on the top of the pipe as required by the drawing.
The pipe was in contact at top and bottom.
The final two welds on the box support (9/16 fillet typical) appear to have an unacceptable surface finish. This is an unresolved item pending engineering review of allowable final clearance. (354/79-02-02)
Support H04 was found to have fillet welds on the angular support
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member that are questionable as to validating fillet weld require-ments. The welds connect members at an angle of approximately 1500 The NRC inspector discussed this concern with the licensee.
This is an unresolved item pending engineering review for accept-ance criteria or corrective action.
(354/79-02-03)
5.
Calibration of M&TE The inspector reviewed P-DM records of calibration of gages, meters, thermometers and MT equipment for conformance to the requirements of the P-DM QA Manual.
The inspector also examined selected items of M&TE including items used as calibration standards to determine whether they were within the established calibration period and that calibration stickers were attached and identified the required calibration due date.
No items of noncompliance were identified.
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6.
QC Records The inspector examined the QC records of fabrication and tests as shown below for conformance to the requirements of Specification C-152(Q) and the P-DM QA Manual and Test Procedures.
Fabrication Check Lists (FCL) No. 1, 2 and 58.
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Fabrication Check List Addenda (FCA) identified on the above
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FCL's.
The FCL's identified applicable drawings, welding and test procedures; inspection points for P-DM QC and " Hold" points for inspection by the Authorized Nuclear Inspector (ANI); Corrective Action Required (CAR) and Engineering CAR's (ECAR), Inspection and " Hold" points had been signed by QC or ANI as appropriate.
NDE had been performed in accordance with the applicable procedures and the test results were included in the. records package. A random selection of test reports was examined by the inspector together with the certifications, eye examination and qualification records of the NDE inspectors.
No items of noncompliance were identified.
7.
Soray Header Supports The inspector observed welding in. progress for attachment.of Spray Header Support Knife Plates No. 2 and No. 20 to the Dry Well as shown on P-DM Drawing E-7.
Welders cerformed the'6ork per Weld Procedure 68-5.. The Walder Qualification List in possession of tite foreman showed the men currently qualified.
No items of noncompliance were identified.
8.
Subcontractor Surveillance A subcontract for fabrication and installation of Safety / Relief Valve Discharge Lines, Nozzle Extensions and Spray Headers had been awarded by P-DM to Schneider, Inc. of Pittsburgh, Pennsylvania.
The Schneider " Nuclear Site Quality Assurance Manual" had been approved by P-DM in accordance with P-DM letter to Schneider dated January 16, 1979.
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The inspector reviewed P-DM Procedure SPS-1, Revision 1, " Surveillance Plan for P-DM Subcontractors" and P-DM Surveillance Inspection Reports since January 29, 1979.
No items of noncompliance were identified.
9.
Pipe Support and Restraint Systems - OA and Work Procedures a.
The Bechtel and PSE&G Quality Assurance procedures were examined for the following attributes:
Establishment of QA audit procedures for pipe supports,
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including scope, frequency of audits, audit criteria and reporting requirements; Establishment of design and procurement documentation
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verifying material, component specifications, and accept-ance criteria;
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Establishment of controls to verify design and field
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changes; and, Establishment of inspection procedures to assure quality
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requirements are met, including documentation that quality requirements of materials and components are met prior to installation or use.
The following documents were reviewed with respect to the above attributes:
Bechtel QA Policy, Quality Audit System, Ravision 4,
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2/13/78; PSE&G QAI 18-1, Audits by the QA Department, Revision 7,
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1/23/79; PSE&G QA Audit Schedule, Index Module 1-17-1, Site Fabrica-
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tion and Installation of Pipe Hangers; Bechtel QA Policy, Home Office Procurement Documents, Revis-
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ion 3A, 8/1/77; Bechtel QA Policy, Supplier Evaluations-Home Office, Revis-
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ion 2A, 8/1/77; 2266
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Bechtel QA Policy, Supplier Control and Source Surveillance,
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Revision 3A, 8/1/77; Bechtel QA Policy, Supplier m ument Processing, Revision 3,
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7/20/77; Bechtel QA Policy, Field Procurement, Revision 4,7/20/77;
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PSE&G QAI 7-1, Procurement Control, Revision 6,2/16/79,
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including the QAI seven series, 7.2 Revision 5, 7.7 Revis-ion 0;
' Bechtel QA Program Description, June 24, 1974, Project
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Engineering, page 14; Document Control, page 31; Bechtel SWP/P-5, Field Change Request Field Change Notice,
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Revision 3, 1/23/79 (FCR, FCN and DCN);
Bechtel SWP/P10, Field Design Approval and Control, Revis-
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ion 2, 4/14/78; Bechtel QA Policy, Design Process and Change Control, Re-
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vision 1, 3/1/74; Bechtei OA Policy, Supplier Control and Source Surveillance,
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Revision 3,7/20/77; Bechtel QA Policy, Construction Site Quality Program, Re-
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vision 2, 10/22/75; Bechtel QA Policy, Material Receiving, Storage and Control,
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Revision 5, 2/28/77; Bechtel QA Policy. Field Inspection and Test, Revision 2,
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10/22/75; and, Bechtel SWP/P-14, Material Receipt Storage and Handling,
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Revision 2,11/15/78, and SWP/P-15, Specific Work Plan Procedure, Revision 3,11/15/78.
b.
Bechtel Work Procedures / Specifications and Drawings were reviewed for the following attributes:
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Identification of type and classification of pipe support
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and restraint systems; Identification of location and spacing of the pipe supports
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and restraints; Instructions for fabrication practices performed with
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maintenance of integrity of the material processed; Instructions to assure secure fasteners 3 type and size;
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Inspection of all snubbers and restraints for freedom of
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movement and for defonnation prior to installation; and, Review and approval of welding and associated procedures
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pertaining to pipe supports and restraint systems.
The following documents were reviewed with respect to the above attributes:
Specification P-401(Q), For Material and Hardware For
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Pipe Supports in Nuclear, Critical and Safety Related Service, Revision 4,10/4/78; Specification P-410(Q), For Installation, Inspection and
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Documentation of Pipe Suppo;'ts in Nuclear Service, Revis-ion 2, 1/18/79;
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Specification P-412(Q), For Design and Documentation of
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Pipe Supports in Nuclear Service For Pipe 2 inches and Smaller, Revision 8, 9/28/78; Specification, P-408(Q), For Design and Documentation
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for Pipe Supports in Nuclear Service for Pipe 2 1/2 inches and Larger, Revision 2, 4/13/78; Specification C-133(Q), For Purchase of Metal for ASME
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Component Supports, Revision 2, 10/13/78; Specification C-130(Q), For Structural Field Welding
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Procedures, Up to Addendum 4,1/18/79; Specification G-003, For Welding Shop and Field Fabrica-
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tion Equipment and Tanks, Revision 4,8/23/78; 2266 345
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Specification C-134(Q), For Purchase of Steel Anchor Bolts
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and Category I Structures, Revision 6, 2/2/79; Specification C-136(Q), For Installation of Expansion Type
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Anchors, Revision 1, 2/22/78; QC1 P-2.10 and P-2.00, QCl W-1,00, QClR W-1.00; and,
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Filler Metal Withdrawal Authorization - WR6, Revision 0.
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No items of noncompliance were identified.
10.
Storage of Pipe Supports The inspector visually examined ten spring pipe supports for damage, cleanliness, rod diameter required size, approximate hot and cold position indication, position lock device and appearance of welds.
The selection consisted of more than three different load ratings, variable spring, four compression type and six tension type. The following identifies the supports examined:
Approximate Support Identification Hot - Cold Set Tension Compression AP-021-H16 725 702 X
BE-017-H01 3500 3475 X
BE-018-H01 2025 1975 X
BE-008-H07 1430 1580 X
BE-044-H01 1290 1200 X
BE-022-H05 230 240 X
BJ-003-H31 1530 1360 X
BE-047-H01 1285 1240 X
BE-046-H01 1280 1240 X
BE-045-H01 1280 1250 X
No items of noncompliance were identified.
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11.
!.'aresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, or items of noncompliance. Unresolved items identified during the inspection are discussed in Paragraphs 3 and 4.
12.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on March 1,1979. The inspector summarized the scope and findings of the inspection.
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