IR 05000361/1979010
| ML13309A691 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/20/1979 |
| From: | Elin J, Haynes R, Pate R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13309A689 | List: |
| References | |
| 50-361-79-10, 50-362-79-10, NUDOCS 7906210347 | |
| Download: ML13309A691 (7) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
.REGION V 50-361/79-10 Report N /79-10 50-361 CPPR-97 Docket N License N CPPR-98 Safeguards Group
.Licensee:
Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770 7Facility Name:
San Onofre Units 2 and 3 1Inspection at:
Construction.Site, San Diego County. California Inspection conducted:
March 1-31, 1979 Inspectors:
411
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_
_
1_
_
J. 0. Elin'1 Reactor Inspector R.. J Pate,G Resident Reactor Inspector Date Signed pproved By:
/at
,1 Date Signed R. C. Hayn s, Chief, Projects Section, Reactor Construction and Engineering Support Branch Summary:
Inspection on March 1-31, 1979.(Report.Nos. 50-361/79-10 and 50-362/79-10)
Areas Inspected:
Routine, unannounced inspection by the resident inspector and a regional based inspector of construction activities including:
safety related electrical component receiving, storage and installation; environmental qualification of electrical penetration assemblies and electrical connector assemblies; piping storage, fit-up, grinding operations and nondestructive testing; reactor pressure vessel and internals protection; reactor internals installation; followup on item reported per 50.55(e); licensee corrective actions on previous inspection findings; and general work in progress. The inspection involved 83 inspector-hours onsite by two NRC inspector Results:
Of the seven areas inspected, no items of noncompliance or deviations were identifie RV Form 219 (2)
7906210 3/7
DETAILS Individuals Contacted a. Southern California Edison Company (SCE)
.+=*P. A. Croy, Site Quality Assurance/Quality Control Supervisor R. Frick, Quality Assurance Engineer
.+=*L. 0. Hamlin, Project Manager
=*R. R. Hart, Construction Superintendent J. Huey, Quality Assurance Engineer P. R. King, QA Engineer
- H. S. Leasure, Chief, Contract Construction Management
+=*D. E. Nunn, Manager, Quality Assurance J. J. Pantaleo, Quality Assurance Engineer F. Pimentel, Quality Assurance Engineer
+=*H. B. Ray, Project Management
+=*L. L. Seyler, Project Quality Assurance Supervisor M. Rodin, Quality Assurance Engineer
+=*W. F. Rossfeld, Quality Assurance Engineer
+D. B. Schone, Lead Engineering Site Representative
+L. D. Tipton, Nuclear Engineering Site Representative b. Bechtel Power Corporation (Bechtel)
=*J. E. Bashore, Division Quality Assurance Manager
+=*C. A. Blum, Quality Control Manager
=*J. R. Caldwell, Project QA Supervisor
+=*R. H. Cutler, Project Field Engineer
+=*J. E. Geiger, Project Field Quality Assurance Supervisor G. Jacobsen, Quality Control Inspector
- W. D. Nichols, Assistant Project Field Engineer J. L. Ruud, Lead Quality Assurance Engineer
- R. W. Welcher, Project Quality Assurance Engineer In addition, construction craftsmen, engineers and foremen were contacted during the inspectio *Denotes attendees at management meeting on March 9, 197 =Denotes attendees at management meeting on March 16, 197 +Denotes attendees at management meeting on March 30, 197 Construction Status The licensee reported that site construction work is 66% complete as o March 29, 1979. The licensee's project management personnel estimate that the construction effort is split 60%/40% between Units 2 and. Licensee Action on Previous Inspection Findings The inspector examined the corrective action taken by the licensee on the following outstanding item a. (Closed) Open Item (50-361/77-10): Documentation of Special Mirror Image Design Revie The results of the mirror image review for the mechanical components was included in the inspection report 50-361/78-1 The results <of the mirror image design review for the electrical systems and component was reviewed by the inspector. The inspector found that Bechtel identified changes required in the routing of the Unit "3 ex-core detector conduit and drawings to show the correct locations of the Unit 3 speed sensors and reactor coolant system instrumentation. Bechtel initiated corrective actions on these items which are under the control of the Bechtel and SCE QA Program The inspector had no further questions on this matte b. (Closed) Open Item (50-361/78-18/01): 480 Volt Switchgear Cabinet 2BO4 Anchor Bolt Interferenc The license's followup on the interference between the circuit breaker motors and the cabinet anchor bolts revealed that a simular situation existed in a total of 29 circuit breaker cabinets. The licensee took action to shorten the anchor bolts, which removed the interference, and advised the Engineering group to insure all future cabinets would not have this discrepancy. The damaged circuit breaker motor was replaced with a spare unit. The inspector had no further questions on this matte. Review of Safety Related Electrical Penetration Assemblies and Electrical Connector Assemblies The licensee's program to establish qualification of electrical penetration assemblies (EPA) and electrical connector assemblies (ECA) was reviewe This review included documentation of seismic and environmental qualifica tion testing of both modular and canister type penetration assemblies and certain co-axial cable connectors. The documents indicated that the equipment met the specification requirements for performance during the qualification testin It was verified that normal service condition aging was simulated prior to the design basis event environmental qualification test The licensee's review of EPAs and ECAs, which would have to withstand the design basis event environmental qualification tests, identified certain co-axial connectors manufactured by Cannon and Amphenol for which qualifi cation documentation was not available at the time of the inspection. The
-3 licensee was aware of this situation and had reported it to Regional Office by letter in January 1979. The required qualification documentation was expected in March 1979 and the licensee stated that it would be brought to the attention of the resident inspector when it arrived. This item will be examined during a future inspectio (50-361/79-10-01)
The installation and maintenance of several electrical connector assemblies was reviewed. The inspector found that the installation and maintenance activities were accomplished in accordance with the manufacturer's recommenda tion The inspector observed that on the containment side of the penetra tions inspected, the terminal strip connectors had been removed and various forms of splices were scheduled to be made in their place. Although an examination was made of the installation procedure which detailed bolted, butt, and parallel type splicing (Bechtel CS-E03 Electrical Construction specification), the actual splicing had not yet started and, therefore, could not be examined. Additionally, environmental qualification tests for these splices, including splice installation, were not reviewed. Thi item will be examined during a future inspection. (50-361/79-10-02)
,5. Safety Related Electrical Components Storage, Handling and Protection Receipt/storage areas, and areas where safety related electrical switchgear and battery equipment were installed, were toured to verify that the requirements of ANSI N45.2.2 (Handling and Storage)
and ANSI N45.2.3 (Housekeeping During the Construction Phase of Nuclear Power Plants), and NRC Regulatory Guides 1.38 and 1.39, as implemented by Bechtel WPP/QCI 008, Appendix II, Storage of Electrical Equipment, were being met. The inspector found that the storage and protection of safety related electrical switchgear met these requirement Instal ation The inspector reviewed conformance to design requirements for installation of various electrical components. Components included in this review were: (1) Battery Rack 3BO09A, which was not fully installed; (2) 4160 Volt Switchgears 2A06 and 2AO4; (3) 4170 Volt to 480 Volt Transformer 2B06X; and (4) 480 volt Switchgear 2B06, which had been turned over to startu The review included documentation of inspection of weldments and torquing of bolts as required by the manufacturer's installation procedure. Also, records of required electrical tests were examined, and the equipment was inspected to verify the accuracy of installation documentation. In addition, calibration records of torque wrenches used were examined to verify that the wrenches were in calibration at the time of installatio No items of noncompliance or deviation were identifie c. Review of Equipment Turnover to Startup The procedures used to insure that items identified during receipt or construction as nonconforming were identified at turnover to the startup organization per 10 CFR 50, Appendix B, Criteria XIV, which requires the establishment of measures to preclude inadvertent bypass ing of required inspections and tests, were reviewed by the inspecto The documents examined included:
(1) The startup and test program manual, test instruction 17, Rev. 4, January 3, 1979, and (2)
the field control, and <quality control manual, construction/startup turnover pro cedure, no.,800, Rev. 0, July 19, 1978. Both of these precedures required identification of all outstanding nonconformance items prior to turnove The inspector "tracked" several nonconforming items which had been ideitified on switchgear at receipt or during installation and found that the items had either been corrected or identified as a deficiency at turnove No items of deviation or noncompliance were identifie d. Review of Document Control The inspector reviewed approximately 15 controlled drawings, selected at random, being used in the field by construction craftsmen working on safety related electrical systems to ascertain that the proper revision was being used. The inspector found that the drawings were all of the latest revision in effect at the time of the examinatio. Over-Pressurization of Spent Fuel Liner Leak Chase Channels, 50.55(e) Report The licensee's final report concerning a reportable condition on the over pressurization of the Unit 3 spent fuel pool liner leak chase channels was reviewed by the inspector. The report stated that the fuel pool liner would be "repaired to assure conformance with the design criteria and bases stated in the safety analysis report" and that procedural controls would be estab lished and appropriate training, inspection and audit would be provided. The inspector reviewed the repair documentation, and verified that the procedures were revised to provide additional controls for cleaning with high pressure air. The records for the training of supervisory and crafts personnel and the audit records were also reviewed. All the corrective action committed to by the licensee were completed. The inspector had no further questions on this ite.
Reactor Vessel and Internals Storage The activities for storage of the Unit 2 and 3 reactor pressure vessel and internals were observed by the inspector. The constructor, Bechtel, was controlling the access to the equipment and maintaining protective covers over all openings as required by the construction procedure No items of noncomplaince or deviations were identifie.
Reactor Vessel Internals Installation The inspector observed the installation of the Unit 3 reactor vessel to core barrel snubber plates to ascertain whether this operation was being controlled as required by the licensee's QA program. The operation was being accomplished in accordance with approved procedures and the inspector found that the required QA inspections were performe No items of noncompliance or deviations were identifie R.,
Reactor Coolant Pressure Boundary and Safety Related Piping The piping related construction activities listed below were observed by the inspector to ascertain whether they were conducted in accordance with the licensee's governing procedure Identification Activity System of piping Pipe Storage Reactor Coolant S2-RC-041-lA, Sh. 1 Safety Injection S3-Sl-075-3B, Sh. 3 Nuclear Service Water S3-NW-355-1D, Sh. 1 Grinding Reactor Coolant S3-1201-ML-019, Sh. 1 Chilled Water S3-1513-ML-698 NDE (PT)
Fuel Storage Pool S3-1219-ML-010, Sh. 3, Weld CB NDE (Visual)
Component Cooling S2-1203-ML-094, Water Weld FW BE NDE (Visual)
Steam S3-1301-ML-015, Sh. 1, Weld E NDE (Visual)
Containment Spray S2-1206-ML-033, Sh. 1 Weld F IS
Feedwater South S/G Sparger Plug Weld NDE (MT)
Component Cooling S3-1203-ML-247, Sh. 1 Water Weld E Fitup Chilled Water S3-1513-ML-698, Sh. 1 Weld C The inspector also verified NDE personnel were qualified in accordance with the requirements of SNT-TC-1 No items of noncompliance or deviations. were identifie.
Plant Tour The inspector toured both Units 2 and 3 several times each week during this inspection report period. Particular attention was directed to observing work in progress and availability of supervision and quality control in spectors at the work areas, housekeeping and preservation of equipmen No items of noncompliance or deviations were identifie i1. Management Interview The inspector met with the licensee representatives (denoted in Paragraph 1)
on March 9, 16 and 30, 1979. The scope of the inspections and inspector's findings as noted in this report were discussed. The licensee representa tives had no additional comments.