IR 05000363/1978014
| ML19270E939 | |
| Person / Time | |
|---|---|
| Site: | 05000363 |
| Issue date: | 11/07/1978 |
| From: | Narrow L, Sanders W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19270E938 | List: |
| References | |
| 50-363-78-14, NUDOCS 7901030249 | |
| Download: ML19270E939 (6) | |
Text
{{#Wiki_filter:e .. . . U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 90-161/7a-14 Docket No. 50-363 License No. CPPR-96 Priority -- Category A Licensee: Jersey Central Power and Light Company 260 Cherry Hill Road Parsippany, New Jersey 07054 Facility Name: Forked River Nuclear Station, Ilnit 1 Inspection at: Forked River, New Jersey Inspection condu fed: Octo er 24-26, 1978 Inspectors: NrW d[[4A [ // L. Narrow, Reactor Inspector ddte signed W W G/b,. A..l ~u ev 3 191r W. F. Sanders, Reactor Inspector date' signed date signed Approved by: [g[F6
, R. W. McGaughhief, Construction date sfgned Project Section, RC & ES Branch Inspectivn Summary: Inspection on October 24-26, 1978 (Report No. 50-363/78-14) Areas Inspected: Routine, unannounced inspection by regional based inspectors of the QA program for fabrication and installation of the containment liner, and review of the status of outstanding items.
The inspection involved 40 inspector-hours on site by two NRC regional based inspectors.
Resul ts: No items of noncompliance were identified.
79010302 [ Region I Form 12 (Rev. April 77)
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3.
Field Fabrication of Reactor Pit Liner An inspection was made of the field fabrication area for the assem-bly of the Reactor Pit Liner. The component, when completed, will be a conical structure 41' diameter, 13' 6" high and will be moved and installed in the reactor cavity as a unit.
The following activities in progress were inspected to the requirements of the applicable drawings and specifications: handling, weld joint fit-ups, application of preheat and the welding to join the upper conical plates, inspection of completed welds and welding in progress to weld the vertical tee bar stiffners to the cylindrical section of the liner.
The inspector also observed the fit up of a back up plate 5B shown on drawing E5.
No items of noncompliance were identified.
4.
N.D.E. Personnel Qualifications The inspector reviewed the personnel Qualification records for the two people on site who have N.D.E. responsibilities.
The records were examined to the requirements of P.D.M. written pract'ce Q.A.S.II and SNT-Tc-1A for evidence of Education, experiente train-ing, technical examination, grading and statement of certification.
No items of noncompliance were identified.
5.
Welder Qualification The inspector examined the qualification records for 3 welders to the requirements of ASME Section IX.
The records show that the 3 welders qualified to SMAW, Vertical, Horizontal and overhead using procedures Vert. 65-2, Horiz. 68-4, and Ov. 68-2.
The test plates were examined by radiography.
No items of noncompliance were identified.
6.
Record and Procedure Review The inspector reviewed the following documents for compliance to the requirements of the P.S.A.R: a.
Engineering specification 2700-205 for the fabrication, instal-lation and testing of the containment liner and penetrations.
b.
P.D.M. Qualtiy Assurance manual for Nuclear Power Plant compon-ents (Corporate Field) Revision 1, 7-8-76 with supplement and revisions to 8-22-7. . . DETAILS 1.
Persons Contacted General Public Utilities Service Corporation (GPU)
- T. Corrie, QA Engineer J. Davis, Resident Civil Engineer
- R. F. Fenti, Lead Site QA Auditor
- W. T. Gunn, Project Site Manager
- N. C. Kazanas, Manager of Qualtiy Assurance S. Levin, Supervisor, Site Engineering E. Staples, QC Engineer
- J. C. Thompson, Site QC Supervisor
- R. L. Wayne, Construction QA Manager
- J. E. Wright, Site QA Manager Stone and Webster Engineering Corporation (S&W)
- K. J. Platte, Resident Engineer
- R. L. Wagner, Superintendent of Construction Pittsburgh - Des Moines Steel Company J. Massengale, Site Manager H. Steiger, Site QC Manager
- denotes those present at the exit interview.
The inspector also interviewed other licensee and contractor em-playees during the inspection.
2.
Plant Tour The inspector made a tour of the construction site to observe work activities in progress.
The inspector examined work items for any obvious defects or noncompliances with regulatory requirements and for evidence of quality control of the work.
Specific activities observed by the inspector included material handling, weld seam fitup and welding of containment liner; set up for radiography of a longitudinal seam; field facilities for developing and viewing of radiographic film; removal of defective concrete in north interior wall of Engineering Safety Features Compartment; preparation for concrete placement, Block No.112 of basemat; and concrete curing.
No items of noncompliance were identifie.
c.
Material, receiving, and certifications for 54 pieces of material which included 1.
Receipt Inspection Report, Form QA 746-1 2.
Documentation Check List, Form QA 730-1 3.
Materia. Test Reports 7.
Removal of Defective Cadwelds During the plant tour the inspector observed that a cadweld sleeve had been cut longitudinally and was being removed from the rebar.
The inspector was informed that this method was used for the re-moval of rejected splices in locations having insufficient space to permit cutting out the entire rebar joint.
The inspector was informed that three reject splices had been removed in this manner.
He examined the applicable documentation including inspection reports and an interoffice memorandum from the A-E which identified removal of the cadweld sleeve as the preferred corrective action.
The inspector discussed the need for a detailed procedure for performance of this work with the licensee's representatives who agreed that a procedure would be provided.
This item is unresolved pending review by an NRC inspector of an approved procedure for replacement of reject cadweld joints by this method.
(78-14-01.)
8.
Licensee Action on Previous Inspection Findinos (Closed) Unresolved Item (363/77-01-01): Recalculation of reactor containment design.
Copies of the Forked RiverInterim Peak Contain-ment Pressure Evaluation have been submitted to NRC Division of Project Management with additional information to be supplied in the FSAR submittal.
Detailed review of this question will be con-ducted during the FSAR review.
(Closed) Unresolved Item (363/78-04-02): QA procedures to supple-ment "QA Plan." The inspector examined a random selection of QA procedures and observed thatthe QA plan is referenced where appli-cable and the procedures do control activities affecting quality as prescribed by the "QA Plan."
(Closed) Unresolved Item (363/78-04-03): Evaluation of original equipment storage and maintenance program and conversion to new program. The inspector examined a list of equipment which identi-fies all items of equipment requiring preventive services on site.
The equipment list provides a comparison of maintenance requirements between the old and new programs and upgraded the program to con-form to the manufacturer's requirement (Closed) Unresolved Item (363/78-11-01): Thermoccu ple calibration checklists stamped " Uncontrolled." The inspector discussed the reason for use of this stamp with the licensee's representative and was informed that the calibration cata had been recorded on this checklist with the understanding that it would be transcribed on permanent records of the using organizations.
The inspector observed that the data had been recorded on permanent records.
9.
Licensee Action on IE Bulletins and Circulars The inspector examined records and interviewed licensee represen-tatives to verify that corrective action had been taken with respect to IE Bulletins and Circulars as shown below: Circular 78-15 (Closed): Installation of tilting disc check valves.
This circular had been referred to the A-E.
The inspector examined B&R letter No.13 JC-8-6052 dated Octo-ber 16,1978, whigh identifies tilting disc check valves installed in vertical lines and provided that the design be prepared accordingly.
10.
Procurement of Safety Related Materials The inspector discussed problems identified at other sites with procurement of materials from Modern Suppliers and Manufacturers, Inc.
No m aterials had been purchased to date from this vendor and the inspector observed that this vendor was not listed on the Vendor Rating List dated October 1,1978.
The inspector had no further questions concerning this matter.
11.
General GPU Corporate personnel were on site reviewing the QA/QC program for structural work together with GPU, S&W, and M-K site personnel.
The review is intended to identify deficiencies and establish a program for their rapid correction.
12.
Unresolved Items Unresolved items are matters about which more information is re-quired in order to ascertain whether they are acceptable items or items of noncompliance. An unresolved item disclosed during this inspection is discussed in paragraph. Exit Interview At the conclusion of the inspection on October 26, 1978, a meeting was held at the Forked River site with representatives of the licensee & contractor organization noted in Para 1.The inspector summarized the results of the inspection as described in the report.
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